1edt621885 - international nuclear information system (inis)

SEP 2 9 1897/ i ? \ ENGINEERING DATA TRANSM1TTALP«ge1 of i

1 E D T621885

2. To: (Receiving Organization)

Packaging Engineering3. From: (Originating Organization)

Packaging Engineering4 . Related EDT Ho. :

6218815. Proj./Prog./Dept./Div.:

03E00

6. Design Authority/ Design Agent/Cog.Engr.:

T. Romano

7. Purchase Order No. :

NA8. Originator Remarks:

The attached SEP is being submitted for approval andrelease.

9. Equip./Component No.:

NA10. System/Bldg./Facility:

NA11. Rece-iver Remarks: 11A. Design Baseline Document? [] Yes [X] No 12. Major Assm. Dug. No.:

_ 1 NA13. Permit/Permit Application No.:

NA14. Required Response Date:

NADATA TRANSMITTED

(B) Document/Drawing No. SheetNo.

(D)Rev. (E) Title or Description of Data

ApprovalDesig-nator Trans-

mittalDispo-

HNF-SD-TP-SEP-063 NA Safety Evaluation forPackaging (Onsite)Plutonium RecycleTest Reactor GraphiteCask

SQ 1,2

Approval Designator (F) Reason for Transmittal (G) Disposition <H) & (I)

E, S, Q, D or N/A(see WHC-CM-3-5,Sec. 12.7)

1. Approval 4. Review2. Release 5. Post-Review3. Information 6. Dist. (Receipt Acknow. Required)

1. Approved 4. Reviewed no/comment2. Approved w/comment 5. Reviewed w/comment3. Disapproved w/comment 6. Receipt acknowledged

17. SIGNATURE/DISTRIBUTION(See Approval Designator for required signatures)

[] Approved[] Approved w/comments[] Disapproved w/comments

BD-7400-172-2 (05/96) GEF097

BD-7400-172-1

HNF-SD-TP-SEP-063, Rev. 0

Safety Evaluation for Packaging (Onsite)Plutonium Recycle Test Reactor Graphite Cask

T. RomanoWaste Management Federal Services, Inc., Northwest OperationsRichland, Washington 99352U.S. Department of Energy Contract DE-AC06-96RL13200

EDT/ECN: EDT 621885Org Code: 03E00B&R Code: EX312O02O

UC: 513Charge Code:Total Pages:

K7A21178

Key Words: transfer, PRTR Graphite Cask, 327 Building, 300 Area,Type B, mixed oxide fuel, metal oxide fuel

Abstract: This safety evaluation for packaging (SEP) provides theevaluation necessary to demonstrate that the Plutonium Recycle TestReactor (PRTR) Graphite Cask meets the requirements of WHC-CM-2-14,Hazardous Material Packaging and Shipping, for transfer of Type B,fissile, non-highway route controlled quantities of radioactive materialwithin the 300 Area of the Hanford Site. The scope of this SEP includesrisk, shieldling, criticality, and tiedown analyses to demonstrate thatonsite transportation safety requirements are satisfied. This SEP alsoestablishes operational and maintenance guidelines to ensure thattransport of the PRTR Graphite Cask is performed safely in accordancewith WHC-CM-2-14. This SEP is valid until October 1, 1999. After thisdate, an update or upgrade to this document is required.

TRADEMARK DISCLAIMER. Reference herein to any specific comnercial product, process, or service bytrade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply itsendorsement, recommendation, or favoring by the United States Government or any agency thereof orits contractors or subcontractors.

Printed in the United States of America. To obtain copies of this document, contact: WHC/BCSDocument Control Services, P.O. Box 1970, Hailstop H6-08, Richland UA 99352, Phone (509) 372-2420;Fax (509) 376-4989.

(lease Approval / Date

Approved for Public Release

A-6400-073 (10/95) GEF321


CONTENTS

PART A: DESCRIPTION AND OPERATIONS

1.0 INTRODUCTION A1-11.1 GENERAL INFORMATION . . A1-11.2 SYSTEM DESCRIPTION A1-11.3 REVIEW AND UPDATE CYCLES A1-1

2.0 PACKAGING SYSTEM . A2-12.1 CONFIGURATION AND DIMENSIONS A2-12.2 MATERIALS OF CONSTRUCTION A2-12.3 WEIGHTS AND CENTER OF GRAVITY A2-12.4 CONTAINMENT BOUNDARY A2-12.5 CAVITY SIZE A2-12.6 SHIELDING A2-12.7 LIFTING DEVICES A2-22.8 TIEDOWN DEVICES A2-2

3.0 PACKAGE CONTENTS A3-13.1 GENERAL DESCRIPTION A3-13.2 CONTENTS RESTRICTIONS A3-1

3.2.1 Radioactive Materials A3-13.2.2 Nonradioactive Hazardous Materials A3-1

4.0 TRANSPORT SYSTEM A4-14.1 TRANSPORTER A4-14.2 TIEDOWN SYSTEM A4-14.3 SPECIAL TRANSPORT REQUIREMENTS A4-2

4.3.1 Routing and Access Control A4-24.3.2 Radiological Limitations A4-24.3.3 Speed Limitations A4-24.3.4 Environmental Conditions A4-24.3.5 Frequency of Use and Mileage Limitations A4-34.3.6 Emergency Response A4-3

5.0 ACCEPTANCE OF PACKAGING FOR USE A5-15.1 NEW PACKAGING A5-15.2 PACKAGING FOR REUSE A5-1

6.0 OPERATING REQUIREMENTS A6-16.1 GENERAL REQUIREMENTS '. A6-16.2 LOADING OF CONTENTS INTO THE CASK A6-1

6.2.1 Inner Container Loading A6-16.2.2 Preparing the Cask for Loading A6-16.2.3 Loading Contents into the Cask A6-2

6.3 PREPARATION OF THE CASK FOR SHIPMENT A6-26.4 UNLOADING THE CASK A6-36.5 EMPTY PACKAGING .' A6-3


CONTENTS (cont)

7.0 QUALITY ASSURANCE REQUIREMENTS A7-17.1 INTRODUCTION A7-17.2 GENERAL REQUIREMENTS A7-17.3 ORGANIZATION A7-17.4 QA PLAN AND ACTIVITIES : A7-2

7.4.1 Design Control A7-27.4.2 Procurement and Fabrication Control A7-27.4.3 Control of Operations/Processes A7-27.4.4 Control of Inspection A7-27.4.5 Test Control A7-27.4.6 Control of Measuring and Test Equipment A7-27.4.7 Control of Nonconforming Items A7-27.4.8 Corrective Action A7-37.4.9 QA Records and Document Control A7-37.4.10 Audits A7-3

8.0 MAINTENANCE . A8-18.1 GENERAL REQUIREMENTS A8-18.2 INSPECTION AND VERIFICATION SCHEDULES A8-18.3 RECORDS AND DOCUMENTATION A8-1

9:0 REFERENCES A9-1

10.0 APPENDICES A10-110.1 DRAWINGS A10-110.2 USER BIENNIAL INSPECTION CHECKLIST AND NONDESTRUCTIVE TESTING

OF LIFTING APPARATUS A10-17

PART B: PACKAGE EVALUATION

1.0 INTRODUCTION B1-11.1 SAFETY EVALUATION METHODOLOGY B1-11.2 EVALUATION SUMMARY AND CONCLUSIONS B1-1

1.2.1 Contents B1-11.2.2 Radiological Risk B1-11.2.3 Containment . B1-11.2.4 Shielding B1-11.2.5 Criticality B1-21.2.6 Structural B1 -21.2.7 Thermal B1 -21.2.8 Gas Generation B1 -21.2.9 Tiedown System B1-2

1.3 REFERENCES B1-2

2.0 CONTENTS EVALUATION B2-12.1 CHARACTERIZATION '. B2-1

2.1.1 Fissile Material Content B2-22.2 RESTRICTIONS B2-2


CONTENTS (cont)

2.3 SIZE AND WEIGHT • B2-22.4 CONCLUSIONS B2-22.5 REFERENCES B2-3

3.0 RADIOLOGICAL RISK EVALUATION B3-13.1 INTRODUCTION B3-1

3.1.1 Summary of Results B3-13.2 RISK ACCEPTANCE CRITERIA B3-13.3 DOSE CONSEQUENCE ANALYSIS RESULTS B3-23.4 PACKAGE FAILURE THRESHOLD ANALYSIS B3-23.5 ACCIDENT RELEASE FREQUENCY ASSESSMENT • B3-3

3.5.1 Approach B3-33.5.2 Accident Release Frequency Analysis B3-4

3.6 EVALUATION AND CONCLUSION B3-63.7 REFERENCES B3-73.8 APPENDIX: CHECKLIST FOR REVIEW B3-8

4.0 CONTAINMENT EVALUATION B4-14.1 INTRODUCTION B4-14.2 CONTAINMENT SOURCE SPECIFICATION : . . . B4-14.3 NORMAL TRANSPORT CONDITIONS B4-1

4.3.1 Conditions To Be Evaluated B4-14.3.2 Containment Acceptance Criteria B4-1

4.4 ACCIDENT CONDITIONS B4-14.4.1 Conditions To Be Evaluated '. . . . B4-1

4.5 CONTAINMENT EVALUATION AND CONCLUSIONS B4-14.5.1 Normal Transport Conditions B4-14.5.2 Accident Conditions B4-2

4.6 SUMMARY OF DOSE CONSEQUENCE RESULTS B4-24.6.1 Introduction and Overview B4-34.6.2 Dose Consequence Analysis Methodology B4-34.6.3 Source Term B4-34.6.4 External Dose Due to Photon (Gamma) Exposure B4-44.6.5 External Dose Due to P-Particle Emitters B4-54.6.6 Inhalation and Ingestion Dose B4-54.6.7 Skin Contamination and Ingestion Dose B4-84.6.8 Submersion Dose Due to Gaseous Vapor B4-94.6.9 Special Considerations B4-94.6.10 Total Dose B4-9

4.7 REFERENCES B4-94.8 APPENDICES B4-11

4.8.1 ISO-PC Input File B4-114.8.2 GXQ Input File B4-124.8.3 GENII Input File B4-144.8.4 Checklist for Technical Peer Review B4-174.8.5 HEDOP Review Checklist B4-18

5.0 SHIELDING EVALUATION B5-15.1 INTRODUCTION . , B5-15.2 DIRECT RADIATION SOURCE SPECIFICATION B5-1

5.2.1 Gamma Source B5-15.2.2 Beta Source B5-15.2.3 Neutron Source B5-1


CONTENTS (cont)

5.3 SUMMARY OF SHIELDING PROPERTIES OF MATERIALS B5-25.4 NORMAL TRANSPORT CONDITIONS B5-2

5.4.1 Conditions To Be Evaluated B5-25.4.2 Acceptance Criteria B5-25.4.3 Assumptions B5-25.4.4 Shielding Model B5-35.4.5 Shielding Calculations B5-4

5.5 ACCIDENT CONDITIONS B5-45.5.1 Conditions To Be Evaluated B5-45.5.2 Acceptance Criteria B5-45.5.3 Assumptions B5-55.5.4 Shielding Model . B5-55.5.5 Shielding Calculations B5-5

5.6 CONCLUSIONS B5-55.7 REFERENCES '. B5-65.8 APPENDICES < B5-6

5.8.1 ISO-PC Input Files '. B5-65.8.2 ORIGEN Input File B5-85.8.3 Neutron Dose Calculations • B5-95.8.4 Peer Review Checklist for Shielding B5-10

6.0 CRITICALITY EVALUATION B6-16.1 APPENDIX: CRITICALITY SAFETY ANALYSIS B6-1

7.0 STRUCTURAL EVALUATION B7-17.1 INTRODUCTION B7-17.2 STRUCTURAL EVALUATION OF PACKAGE B7-1

7.2.1 Package Structural Description B7-17.2.2 Chemical and Galvanic Reactions B7-17.2.3 Sizes of Package and Cavity B7-17.2.4 Weight B7-17.2.5 Tamper- Indicating Devices B7-17.2.6 Positive Closure B7-27.2.7 Lifting and Tiedown Devices B7-2

7.3 NORMAL TRANSPORT CONDITIONS B7-27.3.1 Conditions To Be Evaluated . B7-27.3.2 Acceptance Criteria B7-27.3.3 Hot and Cold Evaluation B7-27.3.4 Reduced and Increased External Pressure B7-37.3.5 Vibration B7-37.3.6 Water Spray B7-37.3.7 Compression B7-37.3.8 Inertial Loading B7-37.3.9 Penetration B7-47.3.10 Conclusions B7-4

7.4 REFERENCES B7-47.5 APPENDIX: STRUCTURAL ANALYSIS B7-5

8.0 THERMAL EVALUATION B8-18.1 INTRODUCTION B8-18.2 THERMAL EVALUATION OF PACKAGE B8-1

8.2.1 Package Description B8-1


CONTENTS (cont)

8.3 NORMAL TRANSPORT CONDITIONS THERMAL EVALUATION B8-18.3.1 Conditions To Be Evaluated .- B8-18.3.2 Acceptance Criteria B8-18.3.3 Thermal Evaluation and Conclusions B8-1

8.4 REFERENCE B8-28.5 APPENDIX: PRTR GRAPHITE CASK NTC THERMAL EVALUATION B8-3

9.0 PRESSURE AND GAS GENERATION EVALUATION B9-1

10.0 TIEDOWN EVALUATION B10-110.1 SYSTEM DESI.GN B10-110.2 ATTACHMENTS, RATINGS, AND REQUIREMENTS B10-210.3 REFERENCE B10-210.4 APPENDIX: ENGINEERING SAFETY EVALUATION B10-3

FIGURE

B3-1 Flow Chart for Hanford Site Large Package Truck Accidents B3-5

LIST OF TABLES

A3-1 Maximum Allowable Source Term A3-1

A3-2 Fissile/Fissionable Material Limits in the Plutonium Recycle Test Reactor Graphite Cask . . . A3-2

A3-3 Inner Container Description . A3-2

A4-1 External Container Contamination Limits A4-2

B2-1 Maximum Allowable Source Term B2-1

B2-2 Decay Heat and A2 Calculation for the Plutonium Recycle Test Reactor Graphite Cask . . . . B2-1

B2-3 Fissile/Fissionable Material Limits in the Plutonium Recycle Test Reactor Graphite Cask . . . B2-2

B2-4 Inner Container Description B2-3

B3-1 Risk Acceptance Criteria Limits B3-2

B3-2 Summary of Doses B3-2

B3-3 Failure Thresholds and Conditional Release Probabilities B3-6

B4-1 Summary of Doses (rem) for the Plutonium Recycle Test Reactor Graphite Cask B4-2

B4-2 Plutonium Recycle Test Reactor Graphite Casks Radioactive Inventory B4-4


LIST OF TABLES (cont)

B4-3 P-Particle Dose Rate for Beta Emitters Contributing > 0.01% to the Total Dose B4-5

B4-4 Accident Airborne Release Quantities, Ci B4-6

B4-5 Inhalation and Submersion Dose (reml B4-8

B5-1 Maximum Allowable Shielding Source Term B5-1

B5-2 Neutron Source Term for 175g of 239Pu B5-2

B5-3 Source Parameters B5-3

B5-4 Shielding Parameters B5-3

B5-5 Maximum Dose Rates Around the Plutonium Recycle Test Reactor Graphite Cask B5-4

B5-6 Maximum Dose Rates Around the Plutonium Recycle Test Reactor Graphite Cask forAccident Conditions B5-5


LIST OF TERMS

ANSIARFatmBq/cm2

CFRCicmcm3

DOEDOTdpm/cm2

EDEFFTFftft /s2

gg/cm3

GyGy/hHzIAEAin.kgkmkm/hkPaIb/uC'ilcm2

MAPMeVMFPmimi/hMPamrem/hm/s2

mSv/hNnon-HRCQNTCPCFPIFPFFPNCPPFPRTRpsiQAQLRFSEPSERFSv

American National Standards Instituteairborne release fractionatmospherebecquerels per square centimeterCode of Federal Regulationscuriecentimetercubic centimeterU.S. Department of EnergyU.S. Department of Transportationdisintegrations per minute per square centimetereffective dose equivalentFast Flux Test Facilityfootfeet per second squaredgramgrams per cubic centimetergraygray per hourhertzInternational Atomic Energy Agencyinchkilogramkilometerkilometers per hourkilopascalpoundmicrocuries per square centimetermixed activation productsmegaelectronvoltmixed fission productsmilemiles per hourmegapascalmillirem per hourmeters per second squaredmillisievert per hournewtonnon-highway route controlled quantitynormal transport conditionsprobability of release from crush failureprobability of release from impact failureprobability of release from fire failurePower Reactor and Nuclear Fuel Development Corporationprobability of release from puncture failurePlutonium Recycle Test Reactorpounds per square inchquality assurancequality levelrespirable fractionsafety evaluation for packagingSpecial Environmental Radiometallurgy Facilitysievert


LIST OF TERMS (cont)

Sv/h sievert per hourTBq terabeoquerelTHI Transportation Hazard IndexW wattW/Ci watts per curie


SAFETY EVALUATION FOR PACKAGING (ONSITE) PLUTONIUMRECYCLE TEST REACTOR GRAPHITE CASK

PART A: DESCRIPTION AND OPERATIONS

1.0 INTRODUCTION

1.1 GENERAL INFORMATION

The Plutonium Recycle Test Reactor (PRTR) Graphite Cask is used by B&W Hanford Companyto transport radioactive materials among the 323, 324, 325, 326, 327, and 3270 Buildings. Theradioactive materials most frequently transported among buildings are mixed oxide fuel, metal oxidefuel, and activated structural materials from reactors. The cask will be used to transport Type B,fissile, non-highway route controlled quantities of radioactive materials within the 300 Area of theHanford Site.

This safety evaluation for packaging (SEP) provides the evaluation necessary to demonstratethat the PRTR Graphite Cask meets the requirements for onsite transportation of a Type B package.The packaging meets all WHC-CM-2-14, Hazardous Material Packaging and Shipping, requirements forthe Hanford Site. The scope of this SEP includes risk, shielding, criticality, and tiedown analyses todemonstrate that onsite transportation safety requirements are satisfied. This SEP also establishesoperational and maintenance guidelines to ensure that transport is performed safely in accordance withWHC-CM-2-14.

1.2 SYSTEM DESCRIPTION

The cask is a horizontal, cylindrical, stainless steel transfer cask with 13.7 cm (5.38 in.) of leadshielding. The outside diameter is 35.6 cm (14.0 in!), and the length is 99.0 cm (39.0 in.). The interiorcavity is 7.9 cm (3.1 in.) in diameter and 63.5 cm (25.0 in.) long. The empty weight of the cask is1,089 kg (2,400 Ib), and the maximum gross weight of the cask is 1,202 kg (2,650 Ib).

1.3 REVIEW AND UPDATE CYCLES

This SEP is valid until October 1, 1999. An update or upgrade to this document is requiredbeyond that date.

A1-1


This page left intentionally blank.

A1-2


2.0 PACKAGING SYSTEM

2.1 CONFIGURATION AND DIMENSIONS

The PRTR Graphite Cask is fundamentally a right circular cylinder of lead and stainless steelcomposite construction. The lead is sandwiched between outer and inner stainless steel tubular shells.At each end of the cask is a thick circular pfate that is welded to both inner and outer sheils, whichencapsulates the lead. At the top, closure of the inner cavity is provided by a bolted blind flange withan attached shield plug of composite lead-stainless steel construction. The cask is equipped with amanually actuated, rotating, shielded drum door, which provides closure at the bottom end. None ofthe end closures are sealed. A handling yoke is provided on the cask and welded to the outer shell.Attached to the yoke is a lifting bail, which can be locked into position for lifting and handling of thecask. Support plates are welded to the outer bottom housing to provide support during transport.

The cask is 35.6 cm (14.0 in.) in diameter and 99.0 cm (39.0 in.) in length. Dimensions of theinner cavity are 7.95 cm (3.13 in.) in diameter by 63.5 cm (25.0 in.) in length. Lead between the outerand inner shells provides shielding.

2.2 MATERIALS OF CONSTRUCTION

All structural components are constructed of 304 stainless steel. Lead is used for shielding.

2.3 WEIGHTS AND CENTER OF GRAVITY

The empty weight of the cask is 1,089 kg (2,400 Ib). The maximum weight with contents is1,202 kg (2,650 Ib). The center of gravity of the PRTR Graphite Cask is approximately the geometriccenter of the cask.

2.4 CONTAINMENT BOUNDARY

The containment system consists of the inner container. The cask retains the contents, but isnot considered to be a containment boundary. No credit is taken for containment provided by the cask.

2.5 CAVITY SIZE

The available space within the cask consists of a cylindrical volume 7.9 cm (3.1 in.) in diameterand 63.5 cm (25.0 in.) in length.

2.6 SHIELDING

The interior of the cask is lined with lead shielding, which is 13.7 cm (5.38 in.) thick.

2.7 LIFTING DEVICES

The lifting device consists of two support arms attached to a lifting yoke. Each support arm issecured to the yoke by three % in.-11 stainless steel cap screws and is secured to the cask shell by a% in.-13 stainless steel cap screw. The lifting assembly is positionable and is equipped with a lockingdevice.

A2-1


2.8 TIEDOWN DEVICES

There are no ttedowh devices attached to the cask.

A2-2


3.0 PACKAGE CONTENTS

3.1 GENERAL DESCRIPTION

Materials to be transported in the PRTR Graphite Cask include irradiated structural materialsand solid pieces of irradiated fuel containing uranium and plutonium isotopes.

3.2 CONTENTS RESTRICTIONS

The materials specified in this section are the only materials authorized for shipment in thePRTR Graphite Cask within the 300 Area of the Hanford Site. Contact dose rates shall be less than2.0 mSv/h {200 mrem/h). Gas-generating materials shall not be loaded into the cask. Absorbed andunabsorbed liquids are not authorized for shipment in the cask. Organic materials are not authorizedexcept plastic bags/wrapping.

3.2.1 Radioactive Materials

The cask will transport Type B, fissile, non-highway route controlled quantities of radioactivematerials. Table A3-1 gives the radioactive contents limits for the cask. Fissile limitations are given inTable A3-2 for shipments of fissionable material scrap of various compositions. The source term limitsin Table A3-1 are a result of the limited shielding ability of the cask as described in Part B, Section 5.0.

Table A3-1. Maximum Allowable Source Term.

Material

Fissile materials and a emitters*

Mixed fission products

Mixed activation products

Activity limit

TBq

0.401

13.9

0.185

Ci

10.9

375

5.00

*Fissile/fissionable materials limited bycriticality safety as shown in Part B, Section 2.1.1.

Contents to be transported in the PRTR Graphite Cask shall consist of small pieces or testsamples of irradiated fuel pieces and various activated materials. The contents shall be limited to themaximum allowable source term as shown in Table A3-1. The cask may also be used to transportmetallographic samples and waste from the 327 Facility examination process.

All materials shall be enclosed in an inner container to prevent the spread of removablecontamination. Table A3-3 provides a description of authorized inner containers and their contents.

3.2.2 Nonradioactive Hazardous Materials

No nonradioactive hazardous materials can be shipped in the PRTR Graphite Cask.

A3-1


Table A3-2. Fissile/Fissionable Material Limits in the PlutoniumRecycle Test Reactor Graphite Cask.

Material

235(j

239Pu, 2 3 3U, 237Np, 241Am,2 4 3Am, 244Cm, and 247Cm

242mAm, 243Cm, 245Cm, 249Cf, or251Cf

Limit

275 g* or

175 g aggregate to ta l *

Not analyzed and cannot be shipped in excessof safeguards accountability limits'*

Source: Larson, S. L, 1996, Limits for Fissionable Material in SmallBore Transfer Casks and Lead Pigs (NCS Basis Memo 96-2 to M. Dec, December 30},Battelle Pacific Northwest Laboratories, Richland, Washington.

*Mixtures of fissionable material are possible provided that the sum-of-fractions method shown in PNL (1994} and referenced in Larson (1 996), attached inPart B, Section 6.0, are followed.

PNL, 1994, Criticality Safety, PNL-MA-25, Battelle Pacific NorthwestLaboratories, Richland, Washington.

Table A3-3. Inner Container Description.

Inner container

Pin tubes-tubes and fittings must havea working rating of 20.68 MPa(3000 psi), with an outer diameter of1.3 cm (0.50 in.) or 1.9 cm {0.75 in.).The tubes are welded on one end. ASwagelok* fitting is used as closure.

DOT Specification 2R per 49 CFR178.360

Large solid item put directly into thecask

Contents

Dtspersible solid materials

Dispersible solid materials

Nondispersible solidstructural material andactivated metals putdirectly into the cask**

Examples of contents

Irradiated structural materials; solidpieces of irradiated FFTF, PNC, andN Reactor fuel pins; and small piecesor test samples of irradiated fuel andstructural materials

Irradiated structural materials; solidpieces of irradiated FFTF, PNC, andN Reactor fuel pins; and small piecesor test samples of irradiated fuel andstructural materials in glass or plasticvials with screw cap

Large solid items with fixed surfacecontamination

DOT = U.S. Department of Transportation.FFTF = Fast Flux Test Facility.PNC = Power Reactor and Nuclear Fuel Development Corporation.

*Swagelok is a trademark of the Crawford Fitting Company.* * Surface contamination limits not to exceed 100 times the Table A4-1 limits. Verification by

survey or the use of a fixative, such as paint, is required.

49 CFR 178, 1 997, "Specifications for Packagings," Code of Federal Regulations, as amended.

A3-2


4.0 TRANSPORT SYSTEM

4.1 TRANSPORTER

The transporter consists of a low boy or flatbed trailer and tractor. The trailer shall be rated forthe weight of the loaded cask and have a large enough bed to prevent the cask from protruding overthe edges of the trailer.

4.2 TIEDOWN SYSTEM

The cask shall be centered and placed horizontally on the bed of the trailer for shipment. Thelong axis of the cask shall be centered along the long axis of the trailer.

The package is to be secured in accordance with U.S. Department of Transportationregulations (49 CFR 393.100). The cask is to be secured to the trailer by two sets of tiedowns asshown in Figure 4-1. One set acts as chocks to block and brace the cask from horizontal movement.The other set acts as vertical restraints. There are two 4x4 wood blocks placed at each end of thecask. These 4x4 blocks have a 2x2 nailed to the side at the bottom to form landings for the tiedowns.Each of the chocking tiedowns is looped around the cask from opposite sides of the trailer andattached to the trailer. The chocking tiedowns lay on the landing and bear against the wood blockswhen drawn tight. The vertical restraint tiedowns are placed over the cask on each side of the liftingyoke. These tiedowns are then attached to the trailer on opposite sides and drawn tight.

Figure 4-1. Cask Tiedown Configuration.

4X4 Wood Block

SX2 Wood BlockNailed to 4X4

A4-1


Each tiedown and trailer attachment point must have a minimum working strength of 11,120 N(2,500 Ib). The 2x2 wood blocks must be nailed to the 4x4 wood blocks with a minimum of three 10 dnails. The length of the blocks is specified as the same as the diameter of the cask to within atolerance of 0.32 cm (Va in.).

Alternative configurations that have been shown to meet 49 CFR 393, Subpart I, areacceptable.

4.3 SPECIAL TRANSPORT REQUIREMENTS

4.3.1 Routing and Access Control

The PRTR Graphite Cask is authorized for oiisite transport only within the 300 Area. Transfersshall be made in accordance with WHC-CM-2-14 over a predetermined route.

4.3.2 Radiological Limitations

The dose rate must be less than 2 mSv/h {200 mrem/h) at the surface of the cask, 0.1 mSv/h(10 mrem/h) at 1 m from the cask surface, and 0.02 mSv/h (2 mrem/h) in any normally occupied space.Transport of the PRTR Graphite Cask above these limits is not authorized. The shielding analysis inPart B, Section 5.0, shows the projected dose rates meet these limits for the authorized source term.

External contamination limits for the exterior of the PRTR Graphite Cask are as shown inTable A4-1.

Table A4-1. External Container Contamination Limits.

Contaminant

Beta and gamma emitters and low toxicity alphaemitters

All other alpha-emitting radionuclides

Maximum permissible limits

Bq/cm2

0.4

0.04

/;Ci/cm2

io-6

10'6

dpm/cm2

22

2.2

Source: 49 CFR 173.443, 1995, "Shippers-General Requirements for Shipments and Packagings,"Code of Federal Regulations, as amended.

4.3.3 Speed Limitations

The PRTR Graphite Cask shall not exceed a speed of 8 km/h (5 mi/h) during transport.

4.3.4 Environmental Conditions

In order to reduce the possibility of an accident, there shall be no transfers at temperaturesbelow 0 °C (32 °F) or during periods of dense fog or adverse road conditions (such as snow or ice}.

A4-2


4.3.5 Frequency of Use and Mileage Limitations

A risk analysis was performed on the 327 Building casks to determine mileage limitations. Theresults of the evaluation have determined that transfers shall not exceed a total of 16.0 km {10.0 mi)per year for the 327 Building family of casks, which includes the Special EnvironmentalRadiometallurgy Facility Cask, the Radioactive Waste Disposal Cask, and the PRTR Graphite Cask. Thislimit allows up to 40 transfers of 0.40 km (0.25 mi] per year. This limit does not apply to empty caskshipments.

4.3.6 Emergency Response

Emergency responders shall be notified prior to transfers of the cask. The shipping andreceiving facilities, Radiation Protection, Safety, Packaging Engineering, and Transportation Logisticsshall be notified of all accidents involving radioactive material shipment that result in vehicle damage,container damage, personnel injury, or contamination spread.

A4-3


This page intentionally left blank.

A4-4


5.0 ACCEPTANCE OF PACKAGING FOR USE

5.1 NEW PACKAGING

The PRTR Graphite Cask was originally accepted for use in the 1960s. That acceptance isdocumented in Hazardous Materials Packaging and Shipping Manual (HEDL 1987). The cask has beenused for shipments within the 300 Area for approximately 20 years without incident. The PRTRGraphite Cask has a frequency of use of approximately six transfers per year. No new casks will bemanufactured, so new packaging acceptance requirements do not apply.

5.2 PACKAGING FOR REUSE

In order to continue using the PRTR Graphite Cask, the maintenance and operating plans mustbe followed. A visual inspection for physical damage and corrosion on the cask and a check of theclosing mechanism for proper operation shall occur prior to reuse. These inspections shall bedocumented in accordance with facility operating procedures.

If required, the cask shall be decontaminated prior to use to meet external contamination limitsper Table A4-1.

A5-1



A5-2


6.0 OPERATING REQUIREMENTS

6.1 GENERAL REQUIREMENTS

The following are requirements for the use of the PRTR Graphite Cask. Prior to loading andshipment of the cask, specific operating procedures with appropriate Quality Assurance/Quality Controlhold points shall be written by the user and approved per WHC-CM-2-14. The procedures shallimplement the requirements of this section and the additional requirements found in this SEP.

For loading and unloading operations, the following general requirements shall be performed.

1. Visually inspect the PRTR Graphite Cask for cracks or damage.

2. Visually inspect the lifting attachments for cracks and damage.

3. Verify that radiological contamination limits are within the allowable limits shown inTable A4-1 of this SEP.

4. Verify radiological dose rates are acceptable prior to shipment of the cask inaccordance with Part A, Section 4.3.2, of this SEP. The dose rate limits are 2 mSv/h(200 mrem/h) on any surface of the cask, 0.1 mSv/h (10 mrem/hl at 1 m from thecask, and 0.02 mSv/h (2 mrem/h) in any normally occupied space.

5. Verify that the number of transfers or mileage shipped in a year has not exceeded theamount established by the risk assessment (40 shipments of approximately 0.40 km[0.25 mi] each or 16.0 km [10.0 mi] per year).

6.2 LOADING OF CONTENTS INTO THE CASK

6.2.1 Inner Container Loading

1. Prior to loading contents, visually inspect the inner container to be used.

2. If vials are to be used, visually inspect them for damage.

3. Place cushioning material in the inner container to protect glass vials. Multiple vialsmay be placed in the inner container. Plastic vials may be packaged as glass vials.

4. After placing the vials in the inner container, fill the void spaces with cushioningmaterial.

5. Close the inner container.

6.2.2 Preparing the Cask for Loading

1. Verify that the contents to be loaded into the cask are as authorized in Part A,Section 3.0, of this SEP and that criticality limits have not been exceeded.

2. Verify that the cask is positioned properly at the cell loading port and is ready toreceive the contents. Open the cell loading port.

A6-1


6.2.3 Loading Contents into the Cask

1. Attach the push/pull rod to the rear end of the cask scoop fixture, commonly called thecask boat.

2. Release the locking mechanism and rotate the closure valve 90°.

3. Release the locking pin holding the boat and push the boat into the cell to the desiredposition.

4. Load the materials onto the boat and pull the boat back into the cask. Secure thelocking pin.

5. Rotate the closure valve 90° and secure the locking mechanism.

6. Close the ceil loading port and move the cask away from the cell.

7. Perform radiological dose and contamination surveys to verify levels have not exceededthe limits authorized in Part A, Section 4.0, of this SEP. Decontaminate ifcontamination limits are exceeded. Do not ship if radiological dose has exceeded2 mSv/h (200 mrem/h) on the surface of the cask, 0.1 mSv/h (10 mrem/h) at 1 m fromthe cask, and 0.02 mSv/h (2 mrem/h) in any normally occupied space.

8. Following radiological survey, wrap the ends of the cask with 10-mil plastic and tape tothe cask body using duct tape.

6.3 PREPARATION OF THE CASK FOR SHIPMENT

1. Verify that the shipping papers have been prepared properly and the cask is properlymarked and labeled per the requirements of WHC-CM-2-14.

2. Position the transport vehicle where it will be accessible to the overhead crane.

3. Verify the lifting equipment is in accordance with the Hanford Site Hoisting and RiggingManual, DOE/RL-92-36 (RL 1996).

4. Attach the lifting equipment to the cask lifting attachment and the crane hook.

5. Lift the cask from the floor to allow a radiological survey of the cask to be performed.

6. Move the cask over the vehicle and slowly lower it into position on the transportvehicle.

7. Unhook the lifting equipment from the cask and install tiedown attachments per therequirements of Part A, Section 4.2.

8. Prior to transport, verify that the shipping documentation has been completed perWHC-CM-2-14 and signed by a trained Hazardous Material Shipper.

A6-2


6.4 UNLOADING THE CASK

1. Position the transport vehicle where it will be accessible to the overhead crane.

2. Perform radiological contamination and dose surveys of the cask to verify that thelimits in Part A, Section 4.0, have not been exceeded.

3. Remove the tiedown equipment from the cask and transport vehicle.

4. Attach the lifting equipment to the cask lifting attachment and the crane hook.

5. Lift the cask off of the transport vehicle and move to a designated location. Removethe plastic from the ends of the cask.

6. Perform a radiological contamination survey of the cask ends to verify thecontamination limits have not been exceeded.

7. Position the cask at the cell loading port and remove the rigging equipment from thecask.

8. Open the cell loading port.

9. Attach the push/pull rod to the rear end of the cask scoop fixture, commonly called thecask boat.

10. Release the closure valve locking mechanism and rotate the closure valve 90°.

11. Release the locking pin holding the boat and push the boat into the cell to the desiredposition.

12. Unload the materials from the boat and pull the boat back into the cask. Secure thelocking pin.

13. Rotate the closure valve and secure the locking mechanism.

14. Close the cell loading port and move the cask away from the cell.

15. Perform radiological dose and contamination surveys to verify levels have not exceededlimits authorized in Part A, Section 4.0, of this SEP. Decontaminate if contaminationlimits are exceeded.

6.5 EMPTY PACKAGING

To be transported as an empty radioactive container, the cask must be prepared for transport inaccordance with 49 CFR 173.428 (1995 version).

A6-3



A6-4


7.0 QUALITY ASSURANCE REQUIREMENTS

7.1 INTRODUCTION

This section describes the quality assurance (QA) requirements for operation of the PRTRGraphite Cask. The packaging was fabricated in the 1960s following a quality program in effect at thetime. The PRTR Graphite Cask is used to perform onsite shipments at the Hanford Site. The formatand requirements for the use of the PRTR Graphite Cask on the Hanford Site are in accordance withWHC-CM-4-2, Quality Assurance Manual, and WHC-CM-2-14.


These requirements apply to activities, which include loading, unloading, and transportationoperations, that could affect the quality of the packaging and associated hardware. The overal!packaging is classified per WHC-CM-2-14 as a Transportation Hazard Index (THI) 1.

THI 1 packaging systems, defined in WHC-CM-2-14, represent the highest level of hazard forthe contents. A packaging system assigned this level has the potential of causing a dose consequenceto an individual in excess of 25 rem at the Hanford Site boundary if fully released.

Each THI invokes a quality level (QL] designator (defined in WHC-CM-2-14) consisting of twoparts: an alpha designator and a numerical designator. The alpha designator assigns the fabrication,testing, use, maintenance standards, and quality requirements for each component of the packagingsystem. The numeric designator following the letter is the THI number of the packaging system.Because the PRTR Graphite Cask ships a Type B quantity of material with potentially high hazards, thepackage as a whole is assigned a QL designator of A-1.

Documentation and review requirements are based upon the QL of the package. Changes ordiscoveries of noncompiiance for all QL A-1 components and activities shall be reviewed by theunreviewed safety question screening process to ensure the quality and safety of the change ordiscovery. Changes to the SEP safety bases (contents, shielding, structural, containment, criticality)will require unreviewed safety question screening regardless of QL.

7.3 ORGANIZATION

The organizational structure and the assignment of responsibility shall be such that quality isachieved and maintained by those who have been assigned responsibility for performing the work.Quality achievement is to be verified by persons or organizations not directly responsible for performingthe work.

Packaging Engineering and the onsite user are responsible for the quality of the work performedby their respective organizations and for performing the following activities:

• Follow the current requirements of this SEP, WHC-CM-4-2, and WHC-CM-2-14• Provide instructions for implementing QA requirements.

The cognizant manager, Quality Assurance, is responsible for establishing and administering theHanford QA program as stated in WHC-CM-4-2.

A7-1


7.4 OA PLAN AND ACTIVITIES

7.4.1 Design Control

Design control is not applicable. This cask was fabricated over 30 years ago, and no designchanges will be made. B&W Hanford Company is the design authority for the package.

7.4.2 Procurement and Fabrication Control

Procurement and fabrication control is not applicable. This package is over 30 years old, andno casks will be procured in the future.

7.4.3 Control of Operations/Processes

' Loading/unloading procedures written by the user will be used to ensure acceptable operationof the packaging. Those loading/unloading procedures shall be consistent with this SEP. Theloading/unloading procedures identify actions required by personnel to safely and properly load andunload the packaging in accordance with this SEP.

Quality Control inspection checklists are established to ensure that final inspection verifiescompliance with the following items.

• The PRTR Graphite Cask is properly assembled.

• All acceptance criteria (Part A, Section 5.0) are met for use of the package.

• Operational (Part A, Section 6.01 and maintenance procedures (Part A, Section 8.0) areproperly completed.

7.4.4 Control of Inspection

Control of inspection and testing will be accomplished by facility procedures incorporating therequirements of Part A, Section 7.4.3.

7.4.5 Test Control

Test control is not applicable. No testing is required on this package.

7.4.6 Control of Measuring and Test Equipment

Any measuring equipment that is used shall meet the accuracy and calibration requirements asrequired by WHC-CM-4-2; i.e., radiation survey equipment.

7.4.7 Control of Nonconforming Items

Identification, documentation, evaluation, and disposition of nonconforming items and activities,shall be accomplished per WHC-CM-4-2, regardless of the assigned QL.

A7-2


7.4.8 Corrective Action

Nonconformance, or conditions adverse to quality, are evaluated as described in Part A,Section 7.4.8, and the need for corrective action is determined in accordance with WHC-CM-4-2.

7.4.9 QA Records and Document Control

Records that furnish documentary evidence of quality shall be specified, prepared, andmaintained per WHC-CM-4-2. This includes all procedures, inspection reports, the SEP, and anynonconformance reports that are developed while this cask is used.

7.4.10 Audits

Internal and external independent assessments are performed in accordance with WHC-CM-4-2.

A7-3



A7-4


8.0 MAINTENANCE


The 327 Facility shall provide the procedures for the required maintenance and inspections ofthe PRTR Graphite Cask.

8.2 INSPECTION AND VERIFICATION SCHEDULES

The PRTR Graphite Cask shall undergo a user inspection every two years. Inspections shall beperformed using the Radioactive Material Shipping Container User Biennial Inspection Checklist (Part A,Section 10.2). Nondestructive testing of the welds on the lifting apparatus shall be performed everyfive years using the Radioactive Material Shipping Container NDT of Lifting Apparatus !5 Year! (Part A,Section 10.2).

8.3 RECORDS AND DOCUMENTATION

The maintenance records shall be maintained for the length of time the PRTR Graphite Cask isowned, plus one year. The inspection records of the PRTR Graphite Cask shall be maintained until thenext inspection of the same type is successfully completed.

A8-1



A8-2


9.0 REFERENCES

49 CFR 173, 1995, "Shippers-General Requirements for Shipments and Packagings," Code of FederalRegulations, as amended.

49 CFR 178, 1997, "Specifications for Packagings," Code of Federal Regulations, as amended.

49 CFR 393, 1997, "Parts and Accessories Necessary for Safe Operation," Code of FederalRegulations, as amended.

HEDL, 1987, Hazardous Materials Packaging and Shipping Manual, MG-137, Rev. 10, HanfordEngineering Development Laboratory, Richland, Washington.

Larson, S. L., 1996, Limits for Fissionable Material in Small Bore Transfer Casks and Lead Pigs iNCSBasis Memo 96-2 to M. Dec, December 30), Battelle Pacific Northwest Laboratories, Richland,Washington.

PNL, 1994, Criticality Safety, PNL-MA-25, Battelle Pacific Northwest Laboratories, Richland,Washington.

RL, 1996, Hanford Site Hoisting and Rigging Manual, DOE/RL-92-36, U.S. Department of Energy,Richland Operations Office, Richland, Washington.

WHC-CM-2-14, Hazardous Material Packaging and Shipping, Westinghouse Hanford Company,Richland, Washington.

WHC-CM-4-2, Quality Assurance Manual, Westinghouse Hanford Company, Richland, Washington.

A9-1



A9-2


10.0 APPENDICES

10.1 DRAWINGS

A10-1



A10-2


! LJI. 11

/.1C Hi.


A1O-7/8

IzCO

I


A10-13/14


10.2 USER BIENNIAL INSPECTION CHECKLIST AND NONDESTRUCTIVE TESTING OFLIFTING APPARATUS

BATTEU.EPacific Northwest Laboratories

Remote Systems Technology Oepartinent

RADIOACTIVE MATERIAL SHIPPING CONTAINERBIENNIAL USER INSPECTION CHECKLIST

Container No: 2701 Inspection Date: Next Inspection Due:

ItemNo.

1.

2.

3.

4.

5.

6.

7.

8.

9.

10.

Spec: Sectionor Dwg; View

H-3-13699Sheet #1

H-3-13699Sheet #1

H-3-13699Sheet #2

H-3-13699Sheet #2

H-3-13699Sheet #1

H-3-13699Sheet #2

H-3-13699Sheet #1

JHB 327-5

JHB 327-5

JHB 327-5

Characteri sti c/Requi rement

Closure "drum" position marked"OPEN" and "CLOSED" on cask.

Closure "drum" handle positionis correct in reference to the"OPEN" and "CLOSED" markings.

Closure "drum" lockingdevice functions properly.

Closure "drum" will closeproperly with transfer "boat"positioned to rear of cask.

Rear locking device holds thetransfer "boat" in position.

Verify that closure "drun"rotates freely.

Verify that locking pin willlock lifting "bail" in thehorizontal/vertical position.

Verify surface is free ofdamage and rust.

Verify that no weld crackingis evident.

Check for loose bolts and/orbroken parts.

Reference orTest Method

VisualInspection

FunctionalTest

FunctionalTest

FunctionalTest

FunctionalTest

FunctionalTest

FunctionalTest

VisualInspection

VisualInspection

VisualInspection

InspectedBy (Init.)

Custodian Siqnature:

A1O-17


BATTELLEPacific Northwest Laboratories

Remote Systems Technology Department

RADIOACTIVE MATERIAL SHIPPING CONTAINERNDT OF LIFriNG APPARATUS (5 YEAR)

Container No: 2701 InsDection Date: Next Inspection Due:

ItemNo.

1.

2.

Spec; Sectionor Dwg; View

H-3-13699Sheet #1

H-3-13699Sheet #1

Characteristic/Requirement

Welds attaching Part #7 to 1"thick Cross Bar.

Welds attaching Part #8 toPart #9.

Test Method

Dyepenetrant

Dyepenetrant

InspectedBy (Init.)

EQUIPMENT TEST INFORMATION

. Ambient . Other .

1. Requester verifies that the equipment to be examined is:Safe.Possible unsafe conditions. ,Radiation - Dose Rate.

2. Anticipated part temperature:

3. Material type to be examined:

4. Area to be inspected:

5. QA Plan:

6. Acceptance Standard:

7. Comments:

. Spot Inspection .Full Inspection (1002 of area requested).

Impact Level: Test Procedure:

8. QA Rep. contacted: Test Date: Time:

Custodian Signature:

A10-18


PART B: PACKAGE EVALUATION

1.0 INTRODUCTION

1.1 SAFETY EVALUATION METHODOLOGY

The Plutonium Recycle Test Reactor (PRTR) Graphite Cask was evaluated against therequirements of WHC-CM-2-14, Hazardous Material Packaging and Shipping, for onsite transportationof solid, Type B, fissile, non-highway route controlled quantities (non-HRCQ) of radioactive materials.The analyses presented in this safety evaluation for packaging verify the PRTR Graphite Cask meetsthe onsite transportation safety requirements based on a risk evaluation.

1.2 EVALUATION SUMMARY AND CONCLUSIONS

As shown by the following evaluations, the PRTR Graphite Cask is safe for the onsitetransportation of solid. Type B, fissile radioactive materials. The cask will prevent loss of contents fornormal transport conditions INTO. A risk evaluation demonstrates that the frequency of an accidentresulting in loss of contents is less than the required criteria of 10'7.

1.2.1 Contents

The typical contents of the PRTR Graphite Cask are evaluated in Part B, Section 2.0.

1.2.2 Radiological Risk

The risk evaluation for the PRTR Graphite Cask demonstrates that the PRTR Graphite Caskmeets the onsite transportation safety criteria. In order to satisfy that criteria, the 327 Building casks,which include the One-Ton Lab Cask, the Long Bore Cask, the Large Bore Cask, the Radioactive WasteDisposal Cask, the Special Environmental Radiometallurgy Facility (SERF) Cask, and the PRTR GraphiteCask, cannot be transported more than a total of 16.0 km (10.0 mil in any calendar year.

1.2.3 Containment

The containment system consists of the PRTR Graphite Cask and the inner container. Theradioactive contents are contained inside the inner container, which is either a glass or plastic vial. Thevials are placed in a slip lid container, which, in turn, is placed in two 10-mil plastic bags that aresealed with duct tape. The plastic vials can also be placed in two 10-mil plastic bags that are sealedwith duct tape. Both types of vials are closed with screw caps. The containment evaluation ispresented in Part B, Section 4.0.

1.2.4 Shielding

The shielding analysis for the source term is presented in Part B, Section 5.0. The caskprovides the shielding required to meet the established radiological dose rate criteria.

B1-1

HNF-SD-TP-SEP-063, Rev. 0-

1.2.5 Criticality

The criticality analysis for the PRTR Graphite Cask is contained in Limits for FissionableMaterial in Small Bore Transfer Casks and Lead Pigs (Larson 1996). The limit for 235U only is 275 g,while the limit for other fissionable materials is 175 g.

1,2.6 Structural

The structural analysis for the PRTR Graphite Cask is contained in Part B, Section 7.0. Thisanalysis shows the PRTR Graphite Cask and the inner containers contain the contents and maintainshielding during all NTC. Accident conditions are addressed in the risk evaluation.

1.2.7 Thermal

The thermal analysis for the PRTR Graphite Cask is contained in Part B, Section 8.0. Thisanalysis demonstrates that the PRTR Graphite Cask performs acceptably during extreme weatherconditions on the Hanford Site.

1.2.8 Gas Generation

The contents of the PRTR Graphite Cask will be dry to prevent gas generation from radiolysis.

1.2.9 Tiedown System

The package tiedown evaluation in Part B, Section 10.0, ensures that the PRTR Graphite Caskwill remain on the trailer under NTC.

1.3 REFERENCES

Larson, S. L., 1996, Limits for Fissionable Material in Small Bore Transfer Casks and Lead Pigs (NCSBasis Memo 96-2 to M. Dec, December 30), Battelle Pacific Northwest Laboratories, Richland,.Washington.

WHC-CIVI-2-14, Hazardous Material Packaging and Shipping, Westinghouse Hanford Company,Richland, Washington.

B1-2


2.0 CONTENTS EVALUATION

2.1 CHARACTERIZATION

Contents to be transported in the PRTR Graphite Cask shall consist of irradiated fuelassemblies, fuel pieces, and various activated materials. The contents shall be limited to the maximumallowable source term shown in Table B2-1.

Table B2-1. Maximum Allowable Source Term.

Material

Fissile materials and a emitters*



Activity limit

TBq

0.401

13.9

0.185

Ci

10.9

375

5.00

*Fissile/fissionable materials limited by criticality safetyas shown in Part B, Section 2.1.1.

The maximum number of A2s and thermal characteristics of the contents, are determined asshown Table B2-2. Note that the isotopes assumed for A2 calculations are for the worst-caseinventory.

Table B2-2. Decay Heat and A2 Calculation for the PlutoniumRecycle Test Reactor Graphite Cask.

Nuclide

90Sr

60Co

239pu

Total

Activity

Bq

1.39E + 13

1.39 E +13

1.85 E +11

4.01 E + 11

2.83 E + 13

Ci

3.75 E + 02

3.75 E + 02

5.00 E + 00

1.09 E +01

7.66 E + 02

Heat productionfactor (W/Ci)

1.16 E-03

5.54 E-03

1.54 E-02

3.06 E-02

Heat generationrate (W)

0.44

2.08

0.08

0.33

2.92

. A2(Ci)

2.70 E + 00

0.00 E + 00

1.08 E + 01

•5.41 E-03

A2s

1.39 E + 02

0.00 E + 00

4.63 E-01

2.01 E + 03

2.14 E + 03

As shown in Table B2-2, the number of A2s is less than 3,000; therefore, the maximumradioactive material inventory is a fissile, Type-B, non-HRCQ (49 CFR 173}.

B2-1


2.1.1 Fissile Material Content

The fissile/fissionable material limits for the PRTR Graphite Cask are shown in Table B2-3.These limits are 275 g of 235U or an aggregate total of 175 g of 239Pu, 233U, 237Np, 241Am, 243Am, 244Cm,and 247Cm. Note that mixtures of fissionable material are possible provided that the sum-of-fractionsmethod shown in Criticality Safety (PNL 1994) is followed.

Table B2-3. Fissile/Fissionable Material Limits in the Plutonium.Recycle Test Reactor Graphite Cask.

Material

235y

2MPu, 233U, a37Np, M 1Am,243Am, 244Cm, and 247Cm

242mAm, 243Cm, 245Cm, 249Cf,or 251Cf

Limit

275 g* or

175 g aggregate total*

Not analyzed and cannot be shipped in excessof safeguards accountability limits*

Source: Larson, S. L., 1996, Limits for Fissionable Material in SmallBore Transfer Casks and Lead Pigs (NCS Basis Memo 96-2 to M. Dec, December 30),Battelle Pacific Northwest Laboratories, Richland, Washington.

* Mixtures of fissionable material are possible provided that the sum-of-fractions method shown in PNL (1994) and referenced in Larson {1996), attached inPart B, Section 6.0, is followed.

PNL, 1994, Criticality Safety, PNL:MA-25, Battelle Pacific NorthwestLaboratories, Richland, Washington.

2.2 RESTRICTIONS

Contents as shown in Part B, Tables B2-1 and B2-3, including daughter isotopes, are the onlycontents authorized for the PRTR Graphite Cask. All contents shall be in inner containers as describedin Table B2-4.

2.3 SIZE AND WEIGHT

Only contents smaller than the internal cavity can be shipped in the PRTR Graphite Cask. Theempty weight of the cask is 1,089 kg (2,400 Ib). The total gross weight of the PRTR Graphite Caskand its contents shall not exceed 1,202 kg (2,650 Ib).

2.4 CONCLUSIONS

The fissionable material limits described in Limits for Fissionable Material in Small Bore TransferCasks and Lead Pigs (Larson 1996) and discussed in Part B, Section 6.0, and the shielding analyses,shown in Part B, Section 5.0, demonstrate that the PRTR Graphite Cask can ship the contents shownin Tables B2-1 and B2-3 safely. The established limits will preclude the possibility of a criticality andminimize radiological exposure to personnel during transport.

As shown in Table B2-2, the maximum quantity of material to be shipped is a fissile, Type Bnon-HRCQ(49 CFR 173).

B2-2


Table B2-4. Inner Container Description.

Inner container

Pin tubes-tubes and fittings must havea working rating of 20.68 MPa(3000 psi), with an outer diameter of

•1.3 cm (0.50 in.) or 1.9 cm {0.75 in.).The tubes are welded on one end. ASwagelok* fitting is used as closure.

DOT Specification 2R per 49 CFR178.360

Large solid item put directly into the.cask

Contents



Nondispersible solidstructural material andactivated metals putdirectly into the cask**

Examples of contents

Irradiated structural materials; solidpieces of irradiated FFTF, PNC, andN Reactor fuel pins; and small piecesor test samples of irradiated fuel andstructural materials

Irradiated structural materials; solidpieces of irradiated FFTF, PNC, andN Reactor fuel pins; and small piecesor test samples of irradiated fuel andstructural materials in glass or plasticvials with screw cap

Large solid items with fixed surfacecontamination

DOT = U.S. Department of Transportation.FFTF = Fast Flux Test Facility.PNC = Power Reactor and Nuclear Fuel Development Corporation.

*SwageIok is a trademark of the Crawford Fitting Company.* * Surface contamination limits not to exceed 100 times the Table A4-1 limits. Verification by

survey or the use of a fixative, such as paint, is required.

49 CFR 178, 1997, "Specifications for Packagings," Code of Federal Regulations; as amended.

2.5 REFERENCES

49 CFR 173, 1997, "Shippers-General Requirements for Shipments and Packagings," Code of FederalRegulations, as amended.

49 CFR 178, 1997, "Specifications for Packagings," Code of Federal Regulations, as amended.

Larson, S. L., 1996, Limits for Fissionable Material in Small Bore Transfer Casks and Lead Pigs (NCSBasis Memo 96-2 to M. Dec, December 30), Battelle Pacific Northwest Laboratories, Richland,Washington.

PNL, 1994, Criticality Safety, PNL-MA-25, Battelle Pacific Northwest Laboratories, Richland,Washington.

B2-3



B2-4


3.0 RADIOLOGICAL RISK EVALUATION

3.1 INTRODUCTION

The 327 Building casks, which include the One-Ton Lab Cask, the Long Bore Cask, the LargeBore Cask, the Radioactive Waste Disposal Cask, the SERF Cask, and the PRTR Graphite Cask, areused to transport Type B non-HRCQs of solid activated metals, irradiated fuel, and other solidradioactive materials among the 300 Area laboratories. Because none of the 327 Building casks arecertified Type B containers, radiological risks are evaluated to determine compliance with onsitetransportation safety requirements per WHC-CM-2-14. Although separate safety documentation hasbeen issued for each cask, the radiological risk evaluation is prepared for the 327 Building casks as acomposite analysis. The composite analysis was prepared due to the similarity in payload, cask type,and transport environment.

The 327 Building casks are used routinely over short distances (less than 0.40 km [0.25 mi])within the 300 Area. The casks are transported by truck.

The assumptions for the radiological risk evaluation are summed as follows:

Highway modeHighway modeApproximately 0.40 km (0.25 mi) per tripA maximum of 24 trips per yearOne cask per shipment.

For accident environments, the 327 Building casks must meet onsite transportation safetyrequirements as outlined in WHC-CM-2-14 and Mercado (1994). The required safety is determined bya radiological risk evaluation that uses dose consequences, risk acceptance criteria, cask failurethreshold values, and Hanford Site accident frequencies. For the evaluation, accidents are categorizedas resulting in impact, crush, puncture, and fire forces. Risk acceptance criteria are outlined in Part B,Section 3.2, and the dose consequence analyses results are provided in Part B, Section 3.3. Caskfailure thresholds are given in Part B, Section 3.4. The analysis of accident release frequencies forassociated failure thresholds is documented in Part B, Section 3.E.- The accident release frequenciesare compared to the risk acceptance criteria determined from the dose consequence analysis toevaluate the acceptability of the risks related to the 327 Building cask shipments.

3.1.1 Summary of Results

Based on the transport of one 327 Building cask per shipment, the dose consequence analysisresulted in a risk acceptance criterion of an annual accident release frequency of less than 10"7. Therelease frequency and conditional probability analysis showed that the criterion is met for shipmentstotaling over 16.0 km (10.0 mi) per year. Therefore, 24 shipments per year of 0.40 km (0.25 mi) eacheasily falls within the range of the acceptable risks as required to meet onsite transportation safety perWHC-CM-2-14. The risk evaluation shows that up to 40 transfers of 0.40 km (0.25 mi) may be madeper year.

3.2 RISK ACCEPTANCE CRITERIA

Graded dose limitations for probable, credible, and incredible accident frequencies ensuresafety in radioactive material packaging and transportation (Mercado 1994). The dose limitations tothe offsite and onsite individual for probable, credible, and incredible accident frequencies are shown inTable B3-1.

B3-1


Table B3-1. Risk Acceptance Criteria Limits.

Description

Incredible

Incredible

Credible

Probable

Annual frequency

< 10 '

10"7 to < 10'6

Iff6 to 103

10'3 to 1

Offsite dose limit*(rem}

None

25

0.5

0.01

Onsite dose limit*(rem}

None

None

5

0.2

•Total effective dose equivalent.

3.3 DOSE CONSEQUENCE ANALYSIS RESULTS

The dose consequence study for the 327 Building casks is presented in Part B, Section 4.0, ofthis safety evaluation for packaging. The analysis does not take credit for the package, rather itfollows International Atomic Energy Agency {IAEA} guidelines and evaluates doses for a release of100% of the material at risk. The accident results are shown in Table B3-2 for a ground-level releaseat the worst location with worst-case (0.5%} meteorology. The doses shown.in Table B3-2 are thetotal committed effective dose equivalents (EDE), which are integrated over 50 years.

Table B3-2. Summary of Doses

Exposure pathway

Total effective dose equivalent

Offsite receptor (rem)

68

Onsite worker (rem)

2000

When compared to the risk criteria given in Table B3-1, the potential dose to the offsitereceptor requires that the 327 Building casks maintain annual accident release frequencies of less than10"7 probability of occurrence per year. Therefore, the annual accident release frequency is limited toless than 10"' per year.

3.4 PACKAGE FAILURE THRESHOLD ANALYSIS

Accident performance of a package is determined by the probability, given an accident, that apackage is subjected to a force more severe than the package failure threshold level for that accidentscenario. For the 327 Building casks, the failure thresholds are assumed to be minimal, and thepackage is assumed to fail if an accident occurs. The failure threshold of the 327 Building casks hasbeen determined for puncture.

• Impact: No impact analysis was performed; the 327 Building casks are assumed to failin the event of an impact.

• Puncture: The puncture failure threshold is based on the equivalent steel thickness ofthe package. The equivalent steel thickness for each of the six casks is at least6.4 cm (2.5 in.). This evaluation is documented in Part B, Section 7.0, page B7-15.

B3-2


Crush: No crush analysis was performed; the 327 Building casks are assumed to fail inany accident involving crush.

Fire: No fire failure analysis was performed, therefore the 327 Building casks areassumed to fail any accident involving a fire.

3.5 ACCIDENT RELEASE FREQUENCY ASSESSMENT

3.5.1 Approach

The accident release frequency assessment is based on the assumption that all failure modesfrom the different forces described as impact, puncture, crush, and fire result in the same level ofconsequence. The union of the package conditional release probabilities from different scenarios withsimilar consequences is multiplied by the frequency of truck accidents to arrive at a total annualaccident release frequency. -

The frequency {F) of a truck accident is the product of the annual number of trips, the numberof miles per trip, and the accident rate per mile.

year trip mite

Hanford Site truck accidents have been compiled in a report using Site-specific data(Green et al. 1996), which gives the accident rate for trucks as 2.0 x 10'7 accidents per mile. For ashipment of radioactive materials that is carried out by trained truck drivers during daylight hours ingood road conditions, a reduction factor of 20 can be applied to lower the rate to 1 x 10"8 (H&R 1995)accidents per mile. Appendix B of Recommended Onsite Transportation Risk ManagementMethodology (H&R 1995) summarizes statistics from the U.S. Department of Transportation (DOT), andthe studies conducted by Sandia National Laboratory on accident responses of small and largepackages. The report recommends reducing truck accident rates by 10 for "safe" truck drivers andanother factor of two for shipment of radioactive material. These reduction factors are based on thefollowing logic.

• Safe truck drivers: Hanford Site truck drivers have special training. Drivers mustcomplete several driver's education courses, have a valid commercial driver's licensewith hazardous endorsement, complete specific training for highway route controlledquantities of radioactive material, and complete radiation worker and hazardousmaterials training. References show that drivers who participate in special safetyprograms reduce single-vehicle accident rates by up to a factor of 100. The H&Rreport (H&R 1995) recommends using an overall accident reduction factor of 10.

• Radioactive material: An additional factor of two is recommended based on the higherlevel of training required for drivers of vehicles carrying radioactive material and thehigher level of caution that would be expected from drivers of cargos consisting ofradioactive material.

After the frequency of accidents is calculated, it is then multiplied by the union of theconditional release probabilities determined in Part B, Section 3.5.2, to arrive at an annual accidentrelease frequency. The annual release frequency is compared to the criteria determined from the doseconsequence analysis (<10'7).

B3-3


3.5.2 Accident Release Frequency Analysis

Information for the probability of occurrence and conditional probabilities of failure is takenfrom Severities of Transportation Accidents Involving Large Packages (Dennis et al. 1978|, Severitiesof Transportation Accidents Volume III - Motor Carriers (Clarke et al. 19761, and H&R (1995).A simplified generic flow chart, shown in Figure B3-1, has been developed using statistics presented inClarke et al. (1976) and Dennis et al. (1978). It visually depicts events that may occur as a result of atruck accident on the Hanford Site. Scenarios, such as immersion, that are not pertinent to theshipment of radioactive material on the Hanford Site are not included. Package failure and materialrelease may occur from fire, impact, crush, and puncture, which for purposes of the joint probabilitycalculations are assumed to be independent events.

The probability of an event in the flow chart, given a preceding event, is determined from thestudies presented with large and small packages in Clarke et al. (1976) and Dennis et al. (1978). Thus,as can be seen in Figure B3-1, the probability of a fire only given a truck accident is 0.0110, and theprobability of an accident resulting in collision or overturn is 0.8935 (Clarke et al. 1976 [p.13]). Trivialaccidents are defined only in terms of the cargo and refer to those accidents that do not affect thepayioad (for example accidents with objects of much lesser mass).

The crush force in the flow chart represents static crush. For large packages inertial crush fallsunder the category of an impact force, and impact failure thresholds are accordingly evaluated foreither impact or inertial crush failure, whichever is the limiting value.. The conditional probability ofstatic crush given a collision or overturn accident is found in Dennis et al. (1978 [p. II-253) as 0.05.This means that 1 in 20 collision or overturn accidents results in static crush to the package. Use ofthe 0.05 value is recommended in Dennis et al. (1978) even though the study states that accidentstatistics indicate a lower rate would be more representative of accident conditions.

The impact environment may result in puncture or impact failure for large packages.Dennis et al. (1978) cites a value of 0.8020 for the probability of an impact or inertial crush force givenan accident. Accordingly, the probability of an impact force occurring given a collision or overturn iscalculated to be 0.8976 (0.8020/0.8935). In a similar manner, the conditional probability of fire givena collision or overturn is calculated from the fire frequency per accident of 1.6% (Dennis et al. 1978[p. 11-15]) and the value for the fire-only scenario of 0.0110. It is worth noting that the statistics inDennis et al. (1978) do not discriminate between fires that affect cargo and fires that do not affectcargo. Therefore, some overconservatism may result from the assumption that all fires affect thecargo.

3.5.2.1 Conditional Release Probabilities. Conditional release probabilities for crush are either 1.0 forfailure or 0 for no failure. In an accident involving crush, for example, failure occurs if the static crushfailure threshold for the package is less than the weight of the truck trailer. No other static crush forcewill occur on the Hanford Site. For the 327 Building casks, the conditional release probability due tocrush-induced failure (PCF) is 1.0 because the casks are assumed to fail in any accident involving crushforces.

The conditional probability of release from failure from fire (PFF) is determined from an H&Rreport {H&R 1995), which incorporates Hanford Site information for emergency response time and fireduration. The value represents the probability that the fire duration is greater than the length of timedetermined to be the failure point for the package. For the 327 Building casks, PFF is equal to 1.0because the package is assumed to fail any fire.

The conditional probability of release from puncture given an impact event (PPF) represents theprobability that an impact event will result in a puncture force large enough to penetrate and fail theequivalent steel thickness of the package. The PPF values are found in Dennis et ai. (1978 [p. M-35]}.The 327 Building casks have an equivalent steel thickness of 6.6 cm (2.6 in), which is rounded downto 6.4 cm (2.5 in.) for a PPF value of 4.36 x 1010.

B3-4

Truck Accidcnt

1 1 0.0110"

Trivial Fire Only

•

1 INo Failure

JOther

ftp-1

Fire Duration > F.T.

0.S935*

Collision or Overturn

0.05*

Crush Force

i iF.T. > Trailer Weight F.T. < Trailer Weight

1No Failure

0.8976°

Impact Force '

.005596*

Fire

1 ! fiF " 1

No Failure Fire Duration > F.T.

^T«4.3(xlS' a j Pjy " 1

Puncture > F.T. Impact > F.T.

Fig

ure

B

3-1.

Flo

So3-to

i ir~SD

or H

J -TP-S

nfo

rc

a 33

I <1 °

, - Portability ofPiieFailra=• Itobabilily of PnnctQie Failorc

Pep =Prol>al)jlityofQnshFaiture

te, 15b)Do»li<, 11-25

« given an aceident) * 0.8976 X 0.S935 = 0.S02O ftom Dratnis, IT-28 and B-85); (0.0110 *• 0.8935(0.005596)J«0.016


The conditional probability of release from impact forces given an impact event (PIF) representsthe probability that the package will be subjected to an impact resulting in a velocity change greaterthan that which could fail the package. As previously stated, inertial crush is included in this category.The values for the impact conditional release probabilities are found in Dennis et al. (1978 [p. 11-23]).For the 327 Building casks, the PIF is conservatively assumed to be 1.0.

Table B3-3. Failure Thresholds and Conditional Release Probabilities.

Force type

Crush

Puncture

Fire

Impact

Failure threshold

Fails crush

6.4 cm (2.5 in.)

Fails any fire

Fails any impact

Conditional releaseprobability

1.0

4.36 x 10"'°

1.0

1.0

3.5.2.2 Joint Probabilities. Conditional release probabilities and failure thresholds are shown inTable B3-3. The joint probability is calculated by taking the union of events (McCormick 1981). Theequation represents the sum of the probabilities of independent events while the subtracted termseliminate double counting arising from the overlap caused by the intersection of the events. Thegeneral equation is given as:

where

and

P(f | a) = the probability of fire given that an accident has occurredP(fc|al = the probability of fire and crush given that an accident has occurred

P(FTE f |f) = the probability that the failure threshold is exceeded by fire given that a fire hasoccurred

then the above equation can be expanded and written as:

P = P(f|a) P(FTEf|f) + P(c|a) P(FTEc|c) + P(l|a) P(FTE l|l) +P(p|a) P(FTE p|p) - P(fc|a) P(FTE f |f) P(FTE c|c) -P(fi|a)P(FTEf|f)P(FTEI|l)-. . .

When substituted in the above equation, the values from the flow chart in Figure B3-1 and theconditional probabilities from Table 3-3 yield a total conditional release probability of 0.978.

3.6 EVALUATION AND CONCLUSION

The total conditional release probability of 0.978 is multiplied by the frequency (F) to arrive atan annual accident release frequency. The annual accident release frequency for 24 shipments of

B3-6


327 Building casks is 5.9 x 10"8. This value is less than the 1 x 10'7 required. In fact, the 327 Buildingcasks can be shipped for up to 16.0 km (10.0 mij per year, and the release frequency is less than thecriterion.

3.7 REFERENCES

Clarke, R. K., J. T. Foley, W. F. Hartman, and D. W. Larson, 1976, Severities of TransportationAccidents, Volume III - Motor Carriers, SLA-74-0001, Sandia National Laboratories,Albuquerque, New Mexico.

Dennis, A. W., J. T. Foley, W. F. Hartman, and D. W. Larson, 1978, Severities of TransportationAccidents Involving Large Packages, SAND77-0001, Sandia National Laboratories,Albuquerque, New Mexico.

DOE, 1994, Airborne Release Fractions/Rates and Respirable Fractions for Nonreactor NuclearFacilities, DOE-HDBK-3010-94, U.S. Department of Energy, Washington, D.C.

Green, J. R., B. D. Flanagan, and H. W. Harris, 1996, Hanford Site Truck Accident Rate, 1990-1995,WHC-SD-TP-RPT-021, Rev. 0, Westinghouse Hanford Company, Richland, Washington.

H&R, 1995, Recommended Onsite Transportation Risk Management Methodology, H&R522-1, H&RTechnical Associates, Inc., Oak Ridge, Tennessee.

McCormick, N. J., 1981, Reliability and Risk Analysis: Methods and Nuclear Power Applications,Academic Press, San Diego, California.

Mercado, J. E., 1994, Report on Equivalent Safety for Transportation and Packaging of RadioactiveMaterials, WHC-SD-TP-RPT-001, Rev. 0, Westinghouse Hanford Company, Richland,Washington.


B3-7


3.8 APPENDIX: CHECKLIST FOR REVIEW

CHECKLIST FOR REVIEW

Document Reviewed: 327 Building Casks Risk Evaluation

Scope of Review: entire document

Yes No NA[ ] [ ] [kd * Previous reviews complete and cover analysis, up to scope of

this review, with no gaps.M - [ ] [ ] Problem completely defined.1x3 [ ] [ 3 Accident scenarios developed in a clear and logical manner.M [ ] [ ] Necessary assumptions explicitly stated and supported.D<] [ ] [ ] Computer codes and data files-documented.\/\ [ ]• [ ] Data used in calculations explicitly stated in document,fii] [ ] [ ] Data checked for consistency with original source information

as applicable.[y] [ ] [ ] Mathematical derivations checked including dimensional

consistency of results.|/] [ ].[] Models appropriate and used within range of validity or use

outside range of established validity justified.M [ ] [ ] Hand calculations checked for errors. Spreadsheet results

should be treated exactly the same as hand calculations.\y] [ ] [ ] Software input correct and consistent with document reviewed.fyt] [ ] [ ] Software output consistent with input and with results

reported in document reviewed.D/] [ ] [ ] Limits/criteria/guidelines applied to analysis results are

appropriate and referenced. Limits/criteria/guidelineschecked against references.

[ ] [ ] Safety margins consistent with good engineering practices.[ ] [ ] Conclusions consistent with analytical results and applicable

. limits.D^] [ ] [ ] Results and conclusions address all points required in the

problem statement.IV] [ ] [ ] Format consistent with appropriate NRC Regulatory Guide or

other standards[ ] [y3 * Review calculations, comments, and/or notes are attached.

[y] [ ] [ ] Document approved.

Reviewer (Printed Name and^gnTture) \ Date

* Any calculations, comments, or notes generated as part of this review shouldbe signed, dated and attached to this checklist. Such material should belabeled and recorded in such a manner as to be intelligible to a technicallyqualified third party.

B3-8


4.0 CONTAINMENT EVALUATION

4.1 INTRODUCTION

The containment system consists of the PRTR Graphite Cask and the inner container. Theinner container can be either a stainless steel tube 1.3 cm (0.50 in.} or 1.9 cm (0.75 in.) in diameter ora DOT Specification 2R container per 49 CFR 178.360. An authorized exception to having an innercontainer would be a large solid item with fixed surface contamination. Items such as described canbe placed directly into the cask. See Table B2-4.

4.2 CONTAINMENT SOURCE SPECIFICATION

The authorized radioactive contents of the PRTR Graphite Cask are described in Part B,Section 2.1. For conservatism, the containment analysis assumes that the inner container consists ofthe two 10-mi! plastic bags, which are placed one inside the other.

4.3 NORMAL TRANSPORT CONDITIONS

4.3.1 Conditions To Be Evaluated

The structural performance of the cask was assessed for the Hanford Site normal conditionsthat are listed in Part B, Section 7.3.1.

4.3.2 Containment Acceptance Criteria

The acceptance criteria for the cask for NTC are that the cask shall retain the inner containerand the inner container (plastic or glass vial} shall retain the radioactive material payload.

4.4 ACCIDENT CONDITIONS


Accident conditions are evaluated for the PRTR Graphite Cask by radiological risk and doseconsequence analyses. The radiological risk evaluation is given in Part B, Section 3.0, of this safetyevaluation. The dose consequence and associated Transportation Hazard Index (THI) are given inPart B, Section 4.6.

4.5 CONTAINMENT EVALUATION AND CONCLUSIONS

4.5.1 Normal Transport Conditions

The PRTR Graphite Cask will provide the structural integrity necessary to transport the payload.The PRTR Graphite Cask has been used for shipments within the 300 Area for approximately 20 years.Prior approval for use of the cask to ship radioactive material was given in MG 137, HazardousMaterials Packaging and Shipping Manual, Rev. 1 (HEDL 1981). Although the PRTR Graphite Cask

B4-1


does not provide containment in the traditional sense, the contents are limited to dry, nondispersibleitems packaged in inner containers that are double wrapped in plastic. The cask provides shieldingand, in conjunction with the inner container and plastic wrapping, prevents the release of the contentsunder the NTC evaluated in Part B, Section 7.0.

4.5.2 Accident Conditions

Based on the radiological risk evaluation in Part B, Section 3.0, and the dose consequenceevaluation given in Part B, Section 4.6, the PRTR Graphite Cask, in conjunction with the other327 Building casks, can be transported a maximum of 16.0 km (10.0 mi) per year while still remainingwithin the acceptable limits for onsite and offsite receptor doses.

4.6 SUMMARY OF DOSE CONSEQUENCE RESULTS

This section documents the dose consequence calculations used to support the THI evaluationfor the 327 Building casks. Six casks are used to transport radioactive materials among severalbuildings in the 300 Area. The casks used for these transfers are the One-Ton Lab Cask, the Long BoreCask, the Large Bore Cask, the Radioactive Waste Disposal Cask, the SERF Cask, and the PRTRGraphite Cask. The authorized contents for each of the casks was reviewed, and the PRTR GraphiteCask was found to have the lowest allowable radioactive inventory. The other 327 Building Casks(One-Ton Lab Cask, Long Bore Cask, Large Bore Cask, Radioactive Waste Disposal Cask, and SERF .Cask) have radioactive inventories that exceed that for the PRTR Graphite Cask; therefore, the doseconsequences for the other five casks will be greater than that for the PRTR Graphite Cask. Becausethe PRTR Graphite Cask has to meet the highest level of requirements (i.e., those associated with a THIof 1), the other five casks will also have to meet the requirements for a THI of 1, and no additionalanalysis is required to demonstrate this.

Table B4-1 shows the dose consequence results from each exposure pathway for the maximumauthorized contents for the PRTR Graphite Cask. The table also shows the dose to each receptor,which is obtained by summing the dose contributions from each pathway. Because the offsite workerdose is greater than 25 rem, the packaging must be designed to THI 1 requirements. The criteria for aTHI of 1, as stated in WHC-CM-2-14:

"THI-1: This represents the highest level of hazard from the contents. A packaging systemassigned this level transports material that has the potential of causing a dose consequence, toan individual, in excess of 25 rem at the Hanford site boundary if fully released."

Table B4-1. Summary of Doses (rem) for the PlutoniumRecycle Test Reactor Graphite Cask.

Exposure pathway

External photon dose

External dose from 3-particles

Inhalation and submersion from the airborne transport pathway

Total effective dose equivalent

Hanford Siteworker at 3 m

2.8

5.0

2000

2000

Publicreceptor*

NA

NA

68

68

Note: 100 rem = 1 sievert (Sv).*This receptor is located 100 m N of the 300 Area.

B4-2


4.6.1 Introduction and Overview

Six casks are used to transport radioactive materials among several buildings in the 300 Area.The casks used for these transfers are the One-Ton Lab Cask, the Long Bore Cask, the Large BoreCask, the Radioactive Waste Disposal Cask, the SERF Cask, and the PRTR Graphite Cask. Theradioactive materials most frequently transported among buildings are irradiated Fast Flux Test Facilityand Power Reactor and Nuclear Fuel Development Corporation fuel, spent N Reactor fuel, mixed oxide,metal oxide, activated structural materials from reactors, and cesium chloride capsules.

An estimate of the dose consequences for various exposure pathways is necessary todetermine the THI for the 327 Building casks. Part B, Section 4.6.2, discusses the generalmethodology used to perform the dose consequence calculations. Part B, Section 4.6.3, addresses thesource term, and Part B, Sections 4.6.4 through 4.6.9, summarize the results for various exposurepathways. The analysis assumes the casks will only be transported within the 300 Area.

4.6.2 Dose Consequence Analysis Methodology

IAEA (1990J defines a standardized approach for evaluating transportation packagingrequirements, called the Q-system. The Q-system methods, as outlined in IAEA (1990), have beenincorporated into the document, Report on Equivalent Safety for Transportation and Packaging ofRadioactive Materials (Mercado 1994). This document (Mercado 1994) is used to demonstrate thatonsite shipments meet onsite transportation safety requirements per WHC-CM-2-14.

In the Q-system, the following five exposure pathways are considered: (1) external exposure tophotons, (2) external exposure to p-particles, (3) inhalation, (4) skin contamination and ingestion, and(5) submersion in a cloud of gaseous isotopes. In special cases, such as a-particle or neutron emitters,other exposure routes are considered. In some cases a pathway will be judged to be small with respectto the others, and consideration will be minimal. Modifications to the IAEA scenarios are incorporatedto more closely describe the particular conditions of the shipment. Detailed calculations for thepostulated accident are performed whenever possible. However, in some cases, the IAEA guide's(IAEA 1990) worst-case rules-of-thumb are used.

The Q-system was developed as an all-encompassing generalized methodology using only theisotope as the defining variable. In this report, the specifics of the package are considered. Some ofthe dose pathways may be considered incredible (frequency <10'6/yr), and although these pathwaysare covered in the IAEA guide, they are disregarded in the analysis.

In the IAEA system, the Q-values that are calculated are the radionuclide activitiescorresponding to each exposure route that causes the individual to receive the effective doseequivalent limit. The minimum Q-values define the A2 values for the shipped materials. In the case ofnondispersible materials (limited by the A, values), only the first two Q-values (based on exposure toexternal photon and external beta particles) are used. Note that for all radiation except neutrons,protons, and heavier charged particles (including a-particles), 1 gray (Gy) = 1 sievert (Sv), and 1 rad =1 rem.

There are two receptors of interest in the Q-system. They are the Hanford Site worker and thepublic receptor. The Hanford Site worker is assumed to be located about 3 m from the package. Thepublic receptor is assumed to be located at the nearest point of public access.

4.6.3 Source Term

The authorized contents for the PRTR Graphite Cask are shown in Table B4-2. The externaldose due to gamma exposure was calculated assuming the mixed fission products (MFP) consist of137Cs, and the mixed activation products (MAP) consist of 60Co, which produce the highest gamma

B4-3


dose rates. The external dose due to beta particle exposure was calculated assuming the MFP consistsof 90Sr/90Y and the MAP consists of 59Fe, which produce the highest beta dose rates. The inhalationdose was calculated assuming the MFP consists of 90Sr, the MAP consists of 59Fe, and the fissilematerial consists of 175 g {10.85 CiJ of 239Pu, which produce the highest inhalation dose. The use of175 g of 239Pu bounds the 2-Ci limit for a emitters for the PRTR Graphite Cask. Note that the alphaemitters and fissile material have a negligible impact on the external gamma and beta dose rates due tothe high content of 137Cs, 90Sr, and 6oCo assumed in the analyses.

Table B4-2. Plutonium Recycle Test ReactorGraphite Casks Radioactive Inventory.

Radioactive material

Fissile material and a emitters

Mixed fission products"

Mixed activation products'

Cask (Ci)

10.9

375

5.00

"Mixed fission products; e.g., 90Sr, 137Cs, etc.bMixed activation products; e.g., 60Co, 54Mn, 59Fe

4.6.4 External Dose Due to Photon (Gamma) Exposure

The IAEA scenario assumes that a person is exposed to a damaged transport package followingan accident. The shielding of the package is assumed to be completely lost in the accident. Thisanalysis will be done assuming a person remains 3 m from the source for a period of 15 minutes.

The computer code ISO-PC (Rittmann 19951 was used to calculate the dose rate 3 m from thesource. The fluence-to-dose conversion factors used were the anterior-to-posterior irradiation patternas outlined in American National Standards Institute (ANSI) standard ANSI/ANS-6.1.1-1991(ANS 1991).

It was conservatively assumed that the MFP (375-Ci limit) consisted of 137Cs and the MAP (5-Cilimit) consisted of 60Co for this analysis. The other radioactive materials (a emitters, others, and fissilematerials) will have a negligible contribution to the gamma dose rate compared to that from 137Cs and60Co.

The PRTR Graphite Cask has an internal diameter of 7.94 cm (3.125 in.) and a length of 62 cm(24.5 in.). The source term was assumed to be homogeneously distributed throughout the cavity ofthe cask.

The payload for the PRTR Graphite Cask consists of mainly activated metal structural materialswith a density of 7.86 g/cm3. For this analysis, the source was taken to be iron with a density of'2.0 g/cm3, which is about one-fourth the density of steel. The lower source density is conservative forthis analysis because it results in higher dose rates due to reduced self-shielding and attenuationeffects. Note that the results are not very sensitive to the selection of the source material.

The resulting dose rate from ISO-PC is 11 rem/h (0.11 Sv/h) at 3 m from the unshielded source.Therefore, the maximum total external gamma EDE for the Hanford Site worker is 2.8 rem (0.028 Sv)for a 15-minute exposure period. The ISO-PC input deck is included as Part B, Section 4.8.1.

B4-4


4.6.5 External Dose Due to p-Particle Emitters

Because of the limited range of P-particles relative to that of photons, a shielding factor is usedby the IAEA to account for residual shielding from material such as package debris. Except for thisfactor, no effort is made to account for either self-shielding or shielding from an accurate model of thedamaged package. Shielding and dose rate factors are graphed in the IAEA Safety Guide No. 7(IAEA 1990) as a function of the maximum energy of the p-particle. The IAEA beta dose ratecalculation methods are based on an individual located 1 m from the unshielded source.

This analysis assumes an individual remains at a distance of 3 m from the source for a15-minute exposure period. A factor will be applied to the dose rates calculated using the IAEAmethod to account for the difference between the 1-m distance assumed in developing the shieldingfactors and the 3-m distance in this analysis. This factor was conservatively taken to be 0.333[(1 m/3 ml] since the dose rate falls off between 1/r2 and 1/r, where r is the distance from the source.This also conservatively ignores any attenuation of the beta particles over the 3-m distance.

Table B4-3 shows the p-particle dose calculations for the inventory in Table B4-2, assuming theMFP consists of 90Sr/90Y and the MAP consists of 59Fe. Note that 239Pu and 235U are not beta emitters.The total P-particle dose rate to the skin for an individual located 3 m from the source is2.0 x 103 rem/h (2.0 x 10' Sv/h). This results in a p-particle dose of 5.0 x 102 rem (5.0 Svl to the skinfor a 15-minute exposure. Because the tissue weighting factor for the skin is 0.01 (1CRP 1991), thewhole body EDE is then 5.0 rem (0.05 Sv). Note that 98 .9% of the 3-particle dose is due to the high-energy (2.28 MeV) p-particle emitted by 90Y.

Table B4-3. P-Particle Dose Rate for Beta EmittersContributing > 0 . 0 1 % to the Total Dose.

Isotope

soSr

90y

Activity(Ci)

3.75 E + 02

3.75 E + 02

Activity(Bq)

1.39 E + 13

1.39 E + 13

Branchingratio

1

0.99989

(MeV)

0.54600

2.28390

Dose ratefactor*

1.8 E-04

3.1 E-04

Shieldingfactor"

100

2

Totals for beta emitters contributing > 0.01 %

Totals for all beta emitters

Dose rate(rem/h)0

2.25 E + 01

1.94 E + 03

1.96 E + 03

1.96 E+03

% Dose

1.15

98.85

100.00

100.00

"Dose rate factor in units of Gy/h or Sv/h for a 1-m Ci source from IAEA (1990)."Shielding factor from IAEA (1990)."Note that a factor of 0.333 is applied to the dose rates to account for a source-to-receptor distance of 3 m for this

analysis, versus the 1-m distance assumed in the development of the dose rate factors from IAEA (1990).

IAEA, 1990, Explanatory Material for the IAEA Regulations for the Safe Transport of Radioactive Material,Safety Series No. 7, Second Edition (As Amended 1990), International Atomic Energy Agency, Vienna, Austria.

4.6.6 Inhalation and Ingestion Dose

Radioactive material may be inhaled following an accident due to resuspension or volatizationof radioactive material released from the package. This section addresses the dose received byworkers and the public due to exposure to airborne radioactivity during a postulated accident event.

4.6.6.1 Selection of Airborne Release Fraction. The U.S. Department of Energy (DOE) handbook.Airborne Release Fractions/Rates and Respirable Fractions for Nonreactor Nuclear Facilities(DOE 1994), was reviewed to identify applicable airborne release fractions (ARF) and respirablefractions (RF) for the authorized contents of the 327 Building casks. The PRTR Graphite Cask is only

B4-5


' authorized to transport irradiated structural materials or encapsulated solid materials. DOE {1994}identifies a bounding ARF x RF of 1 x 10'3 for contaminated noncombustible materials not undergoingbrittle fracture during shock vibration. This is a conservative airborne release fraction for the cask-contents considering that the authorized contents specify that "All materials shall be enclosed in aninner container. The type of inner containment shall be sufficient to contain the item and preventspread of removable contamination." Although the casks have not been analyzed to withstandhypothetical accident conditions, the inner container and the thick lead walls of the casks will likelyprevent any catastrophic loss of the cask contents. The accident scenario envisioned for this analysisis an energetic event causing a loss of the cask closure lid, which exposes the cask contents andresults in the radioactivity becoming airborne. No credit is taken for any containment provided by theinner container or the cask.

The ARF x RF of 1 x 10~3 is applied to the material at risk, which is assumed to be the entirecask radioactive inventory, to obtain the quantity of radioactive material that is made airborne for thepostulated accident scenario. As mentioned in Part B, Section 4.6.3, the inhalation dose for the PRTRGraphite Cask is calculated assuming the MFP consists of 90Sr, the MAP consists of 59Fe, and the fissilematerial consists of 175 g (10.85 Ci) of 239Pu, which produce the highest inhalation dose> Theaccident release quantities are listed in Table B4-4.

Table B4-4. Accident Airborne Release Quantities, Ci.

Nuclide

so S r / 9o Y

5 9Fe

239pu

Plutonium Recycle TestReactor Graphite Cask

0.375

0.005

0.011

4.6.6.1.1 Discussion of Integrated Normalized Air Concentration Value (X/Q'). After theradioactive material becomes airborne, it is transported downwind and inhaled by onsite workers or thepublic. The concentration of this material is reduced, or diluted, as it is being transported due toatmospheric mixing and turbulence. X/Q' (s/m3) is used to characterize the dilution of the airbornecontaminants during atmospheric transport and dispersion. It is equal to the time-integrated normalizedair concentration at the receptor. X/Q' i s a function of the atmospheric conditions (i.e., wind speed,stability class) and the distance to the receptor.

Bounding X/Q' values are generated consistent with the methods described in AtmosphericDispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants,Regulatory Guide 1.145 (NRC 1982). Because atmospheric conditions fluctuate, a boundingatmospheric condition is determined to be that condition that causes a downwind concentration ofairborne contaminants that is exceeded only a small fraction of time because of weather fluctuations.Regulatory Guide 1.145 (NRC 1982) defines this fraction of exceedance as 0.5% for each sector or 5%for the overall Hanford Site. The Hanford Site is broken up into 16 sectors that represent 16 compassdirections; i.e., S, SSW, SW, . . . , ESE, SE, SSE. X/Q' values are generated for weather conditionsthat result in downwind concentrations exceeded only 0.5% of the time in the maximum sector or 5%of the time for the overall Site. These X/Q' values are also referred to as 99.5% maximum sector and95% overall Site X/Q' values. The greater of these two values is called the bounding X/Q' value and isused to assess the dose consequences for accident scenarios. The bounding X/Q' value representsminimum dispersing conditions that result in maximum downwind concentrations; i.e., concentrationsexceeded only a very small fraction of the time. This X/Q' value will therefore result in veryconservative estimates of accident consequences.

B4-6


The X/Q' values in this report were generated using the GXQ computer program. Version 3.1C(Hey 1993a, 1993b). The meteorological data used by GXQ are in the form of joint frequency tables.The joint frequency data are the most recent data available; they are nine-year-averaged data(1983-1991) from the Hanford Site meteorology towers located in the 300 Area. The X/Q' values aregenerated using the methods described in Regulatory Guide 1.145 (NRC 1982) for a ground releasewith no credit taken for plume rise, plume meander, plume depletion, or any other models. This isconservative because all of these models reduce the airborne concentration at the downwind receptorlocations.

Although we are interested in the dose to a Hanford Site worker at 3 m, the dose to an onsitereceptor located 100 m from the release point is calculated using the worst-case X/Q' value at 100 m.This dose is then multiplied by a factor of 30 to obtain the dose to the Hanford Site worker at 1 m inaccordance with IAEA (1990). This approach is taken because the Gaussian equation, along with theparameters used to calculate the X/Q' values, are only valid for distances of 100 m or greater.Although this analysis assumes the transport worker remains 3 m from the package, the inhalationportion of the transport worker dose is conservatively taken to be that calculated using the IAEAmethod for a worker located 1 m from the package.

The 327 Building casks will be transported within the 300 Area. The maximum X/Q' value foran onsite receptor is 4.21 x 10"2 s/m3 and occurs for an individual located 100 m N of the release pointin the 300 Area.

The 300 Area is not a public exclusion area. Even though the roads may be closed duringmovement of the 327 Building casks, members of the public may be in the area. Therefore, it isconservatively assumed for this analysis that the public receptor is located 100 m from the releasepoint in any compass direction. The maximum onsite and public receptor X/Q' value will therefore bethe same, i.e., the maximum public receptor X/Q' value is 4.21 x 10'2 s/m3. The GXQ input file for themaximum X/Q' case is listed in Part B, Section 4.8.2. The title of the joint frequency file used by GXQis 300 AREA - 10 M - Pasquill A - G (1983 - 1991 Average).

4.6.6.1.2 Inhalation and Submersion Dose Calculations. Because the GENII computer codeVersion 1.485 (Napier 1988) is the Site standard computer code for environmental release dosecalculations, it was used to calculate the inhalation and submersion dose for the maximum onsjte andpublic receptors. The airborne release quantities used in GENII are shown in Table B4-4. An exampleGENII input deck is listed in Part B, Section 4.8.3. The Worst Case Solubility class library was used,which is the most conservative library. The GENII libraries used were as follows:

• GENII Default Parameter Values (28-Mar-90 RAP)• Radionuclide Library - Times < 100 years (23-July-93 PDR)• External Dose Factors for GENII in person Sv/yr per Bq/n (8-May-90)• Worst Case Solubilities, Yearly Dose Increments (23-Jul-93 PDR).

The EDE from GENII for the inhalation and submersion pathways is 1.2 x 102 rem (1.2 Sv) forthe maximum onsite receptor at 100 m N of the 300 Area. The inhalation dose contribution to the EDEis based on a 50-year dose commitment period. The maximum x/Q' value from GENII was7.4 x 10"2 s/m3 for the maximum onsite receptor. The dose rates calculated by GENII are proportionalto the x/Q' values. The GXQ code calculates the 99.5% maximum sector and 95% overall Site X/Q'values consistent with Regulatory Guide 1.145 (NRC 1982) methods, while GENII is inconsistent withRegulatory Guide 1.145 methods. As mentioned in the previous section, the maximum onsite receptorX/Q' value from GXQ is 4.21 x 10"02 s/m3. Therefore, the EDE for the inhalation and submersionpathways is 6.8 x 101 rem (6.8 x 10"1 Sv) for the maximum onsite receptor at 100 m using the GXQX/Q' value. This value was obtained by multiplying the GENII dose rate by the ratio of the GXQ X/Q'value to the GENII X/Q' value. Therefore the maximum public receptor dose is 6.8 x 101 rem(6.8 x 101 Sv).

B4-7


To compensate for the fact that the onsite dose is calculated at a source-to-receptor distanceof 100 m, this dose is multiplied by a factor of 30 to obtain the dose to the transport worker at 1 m inaccordance with IAEA (1990]. Although this analysis assumes the transport worker remains 3 m fromthe package, the inhalation portion of the transport worker dose is conservatively taken to be thatcalculated using the IAEA method for a worker located 1 m from the package. This results in an EDEof 2.0 x 1O3 rem (20.0 Sv) for the Hanford Site worker. Table B4-5 shows the doses for the postulatedaccident scenario.

Table B4-5. Inhalation and Submersion Dose (rem).

Effective dose equivalent

Hanford worker(at 3 m)

2000

Public receptor*

68

Note: 100 rem = 1 Sv.*This receptor is located 100 m N of the 300 Area.

4.6.6.1.3 Ingestion and Ground Shine Dose. The other potential internal exposure pathway forthe public receptor is the ingestion pathway. Exposure through the ingestion pathway occurs whenradioactive materials that have been deposited offsite during passage of the plume are ingested eitherby eating crops grown in, or animals raised on, contaminated soil or through drinking contaminatedwater. There are DOE; DOE, Richland Operations Office; state; and federal programs in place toprevent ingestion of contaminated food in the event of an accident (RL 1994, WSDOH 1993,WS 1994, EPA 1992). The primary determinant of exposure from the ingestion pathway is theeffectiveness of public health measures (i.e., interdiction) rather than the severity of the accident itself.The ingestion pathway, if it occurs, is a slow-to-develop pathway and is not considered an immediatethreat to an exposed population in the same sense as airborne plume exposures.

The ground shine pathway is an additional potential external exposure pathway for the publicreceptor. Ground shine refers to the external dose received by a person standing on groundcontaminated by radioactive materials deposited during passage of the airborne radioactive plume.Similar to the ingestion pathway, the primary determinant of exposure from the ground shine pathwayis the effectiveness of public health measures (i.e., interdiction) rather than the severity of the accidentitself. The ground shine pathway is a slow-to-develop pathway and is not considered an immediatethreat to an exposed population in the same sense as airborne plume exposures.

Because of the large radioactive inventory contained in the casks, it is argued that in the eventof an accident scenario that results in the release of a large portion of the inventory, interdictivemeasures (RL 1994, WSDOH 1993, WS 1994, EPA 1992) would be taken to prevent ingestion ofcontaminated food and exposure through the ground shine pathway. Therefore, the ingestion andground shine pathway doses were not calculated in this report.

4.6.7 Skin Contamination and Ingestion Dose

In the IAEA guide (IAEA 1990), it is assumed that 1 % of the package contents are spread overan area of 1 m2 and handling of debris results in contamination of the hands to 10% of this level. It isfurther assumed that the worker is not wearing gloves but that he recognizes the possibility ofcontamination and washes his hands within five hours. The effective dose equivalent to the skinreceived by the individual is estimated from a graph provided in the IAEA guide.

The IAEA scenario for the uptake of activity due to ingestion of the material assumes that theperson ingests all of the contamination from 10 cm2 of skin over a 24-hour period. Because the dose

B4-8


per unit uptake via inhalation is generally the same order or larger than that via ingestion, the inhalationpathway will normally be limiting for internal contamination due to P-ray emitters. In particular, if theskin contamination dose is much larger than the inhalation dose, the ingestion pathway is notconsidered.

Both these pathways are ordinarily neglected when calculating the dose consequences from anonsite transportation accident. The transportation workers are trained in the appropriate response toprotect themselves from experiencing unnecessary radiation exposure, including preventing skincontamination and ingestion.

4.6.8 Submersion Dose Due to Gaseous Vapor

This exposure pathway is caused by submersion in a cloud of gaseous isotopes that are nottaken into the body. A rapid release of 100% of the package contents is assumed. The IAEA guide(IAEA 1990) concentrates entirely on releases within confined structures. No guidance is given foroutside releases.

There are no gaseous vapors present in the cask; therefore, this exposure pathway is notapplicable.

4.6.9 Special Considerations

Alpha particle emitters are not of significance in the material considered in this report. Thealpha particle emitters are of a low concentration, and their effect will be through the mechanism ofinhalation that has been considered separately. Therefore, they are not addressed in this report. Thequantity of radon present in the fuel is insignificant; therefore, radon is not addressed in this report.

The fuel (e.g., plutonium) contained in the casks emits neutrons through (ot,n) and spontaneousfission reactions. These neutron emitters will contribute to the dose received by the Hanford Siteworker, but will have a negligible impact on the public receptor. A conservative estimate of theneutron dose was made using the method described in Nelson (1996). The results indicate that theneutron dose contribution is negligible compared to the gamma dose due to the large MFP and MAPinventory. Therefore, the neutron dose was not calculated separately in this report.

Bremsstrahlung has been included in the consideration of photon effects, and the effects ofshort-lived daughter products have been included in all of the calculations. Where these isotopes aresignificant, they are assumed to be in equilibrium with their longer-lived parent isotopes.

4.6.10 Total Dose

Table B4-1 in Part B, Section 4.6, shows the dose from each exposure pathway.

4.7 REFERENCES

ANS, 1991, Neutron and Gamma-Ray Fluence-to-Dose Factors, ANSI/ANS-6.1.1-1991, AmericanNuclear Society, La Grange Park, Illinois.

DOE, 1994, Airborne Release Fractions/Rates and Respirable Fractions for Nonreactor NuclearFacilities, DOE-HDBK-3010-94, U.S. Department of Energy, Washington, D.C.

B4-9


DOE, 1992, Hazard Categorization and Accident Analysis Techniques for Compliance with DOE Order5480.23, Nuclear Safety Analysis Reports, DOE-STD-1027-92, U.S. Department of Energy,Washington, D.C.

DOE, 1988, Radiation Protection for Occupational Workers, DOE Order 5480.11, U.S. Department ofEnergy, Washington, D.C.

EPA, 1992, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents,U.S. Environmental Protection Agency, Washington, D.C.

HEDL, 1981, Hazardous Materials Packaging and Shipping Manual, MG 137, Rev. 1, HanfordEngineering Development Laboratory, Richland, Washington.

Hey, B. E., 1993a, GXQ Program Users' Guide, WHC-SD-GN-SWD-30002, Rev. 0, WestinghouseHanford Company, Richland, Washington.

Hey, B. E., 1993b, GXQ Program Verification and Validation, WHC-SD-GN-SWD-30003, Rev. 0,Westinghouse Hanford Company, Richland, Washington.

IAEA, 1990, Explanatory Material for the IAEA Regulations for the Safe Transport of RadioactiveMaterial, Safety Series No. 7, Second Edition (As Amended 1990), International Atomic EnergyAgency, Vienna.

ICRP, 1991, International Commission on Radiological Protection, Annals of the ICRP, Publication 60,1991, International Commission on Radiological Protection, New York, New York. •

Mercado, J. E., 1994, Report on Equivalent Safety for Transportation and Packaging of RadioactiveMaterials, WHC-SD-TP-RPT-001, Rev. 0, Westinghouse Hanford Company, Richland,Washington.

Napier, B. A., et al., December 1988, GENII - The Hanford Environmental Radiation Dosimetry SoftwareSystem, PNL-6584, Vol. 1, UC-600, Pacific Northwest Laboratory, Richland, Washington.

Nelson, J. V., 1996, Estimation of Neutron Dose Rates from Nuclear Waste Packages, (internal memo8M730-JVN-96-007 to J. R. Green, March 8), Westinghouse Hanford Company, Richland,Washington.

NRC, 1982, Atmospheric Dispersion Models for Potential Accident Consequence Assessments atNuclear Power Plants, Regulatory Guide 1.145, U.S. Nuclear Regulatory Commission,Washington, D.C.

Rittmann, P. D., 1995, ISO-PC Version 1.98 - User's Guide, WHC-SD-WM-UM-030, Rev. 0,Westinghouse Hanford Company, Richland, Washington.

RL, 1994, Emergency Implementation Procedures, DOE-0223, U.S. Department of Energy, RichlandOperations Office, Richland, Washington. :


WHC-CM-4-46, Nonreactor Facility Safety Analysis Manual, Westinghouse Hanford Company, Richland,Washington.

WHC, 1995, Packaging Design Criteria, Transfer and Disposal of Long-Length Equipment, Hanford TankFarm Complex, WHC-SD-TP-PDC-020, Rev. 2, Westinghouse Hanford Company, Richland,Washington.

B4-10


WSDOH, 1993, "Response Procedures for Radiation Emergencies," Appendix A, Protective ActionGuides, Washington State Department of Health, Olympia, Washington.

WS, 1994, "Fixed Nuclear Facility Emergency Response Procedure," Section 10.6 - Department ofAgriculture, Washington State.

4.8 APPENDICES

4.8.1 ISO-PC Input File

0 2 PRTR Cask Side Dose Rate - UnshieldedCyl. Source Geom - Dose Rate at 3 m Side SurfaceStlnput Next= 1 , ISpec= 3 , IGeom= 7 , IC0NC = 0, SFACT = 1, DUNIT = 7,NTheta= 30, NPsi= 20, NShld= 1 , JBuf = 1, OPTION = 1,Slth= 62.2,Y= 31.1 ,T(1) = 3.969,X= 303.969,WEIGHTI335) = 375 ,WEIGHT(336) = 354.75,WEIGHTI472) = 5, &ISourc 9 2.0End of Input&lnputNext= 6 &

B4-11


4.8.2 GXQ Input File

300 Area - Sector 99.5% X/Q Values - 100 mc GXQ Version 4.0 Input Filec mode

1cc MODE CHOICE:c mode = 1 then X/Q based on Hanford site specific meteorologyc mode = 2 then.X/Q based on atmospheric stability class and wind speedc mode = 3 then X/Q plot file is createdcc LOGICAL CHOICES:c ifox inorm icdf ichk isite ipop

T F F F F Fc ifox = t then joint frequency used to compute frequency to exceed X/Qc = f then joint frequency used to compute annual average X/Qc inorm = t then joint frequency data is normalized (as in GENII)c = f then joint frequency data is un-normalizedc icdf = t then cumulative distribution file created (CDF.OUT)c = f then no cumulative distribution file createdc ichk = t then X/Q parameter print option turned onc = f then no parameter printc isite = t then X/Q based on joint frequency data for all 16 sectorsc = f then X/Q based on joint frequency data of individual sectorsc ipop = t then X/Q is population weightedc = f then no population weightingcc X/Q AND WIND SPEED ADJUSTMENT MODELS:c ipuff idep isrc iwind

0 0 0 0C DIFFUSION COEFFICIENT ADJUSTMENT MODELS:c iwake ipm iflow ientr

0 0 0 0c EFFECTIVE RELEASE HEIGHT ADJUSTMENT MODELS:c (irise igrnd)iwash igrav

0 0 0 0c ipuff = 1 then X/Q calculated using puff modelc = 0 then X/Q calculated using default continuous plume modelc idep = 1 then plume depletion model turned on (Chamberlain model)c isrc = 1 then X/Q multiplied by scalarc = 2 then X/Q adjusted by wind speed functionc iwind = 1 then wind speed corrected for plume heightc isize = 1 then NRC RG 1.145 building wake model turned onc = 2 then MACCS virtual distance building wake model turned onc ipm = 1 then NRC RG 1.145 plume meander model turned onc = 2 then 5th Power Law plume meander model turned onc = 3 then sector average model turned onc iflow = 1 then sigmas adjusted for volume flow ratec ientr = 1 then method of Pasquill used to account for entrainmentc irise = 1 then MACCS buoyant plume rise model turned onc = 2 then ISC2 momentum/buoyancy plume rise model turned onc igrnd = 1 then Mills buoyant plume rise modification for ground effectsc iwash = 1 then stack downwash model turned onc igrav = 1 then gravitational settling model turned onc = 0 unless specified otherwise, 0 turns model offc

c PARAMETER INPUT:c reference frequency

releaseheighths(m)

0.00000E

initialplumewidth

anemometer mixinjheightha(m)

+ 00 1.

initialplumeheight

heighthm(m)

00000E + 01

releaseduration

] toexceed

Cx(%)

1.00000E + 03 5.00000E-01

gravitationaldepositionvelocity

settlingvelocity

B4-12


(m/s) vg{m/s)

O.OOOOOE + 00 0.00000E + 00 0.00000E + 00 1.00000E-03 1.00000E-03cc initial initial convectivec ambient plume plume release heat releasec temperature temperature flow rate diameter rated)c Tamb(C) TO{C) V0{m3/s) d(m) qh{w)c

2.00000E + 01 2.2O000E +01 1.00000E + 00 1.00000E + 00 O.OOOOOE + 00cc {1) If zero then buoyant flux based on plume/ambient temperature difference,cc X/Q Windc scaling Speedc factor Exponent

1 .OOOOOE +00 7.80000E-01cc RECEPTOR DEPENDENT DATA (no line limit)c FOR MODE make RECEPTOR DEPENDENT DATAc 1 {site specific) sector distance receptor-heightc 2 (by class & wind speed) class windspeed distance offset receptor-heightc 3 (create plot file) class windspeed xmax imax ymax jmax xqmin powercc RECEPTOR PARAMETER DESCRIPTIONc sector = 0, 1, 2... {all, S, SSW, etc.)c distance = receptor distance (m)c receptor height = height of receptor {m)c class = 1, 2, 3, 4, 5, 6, 7 (P-G stability class A, B, C, D, E, F, G)c windspeed = anemometer wind speed {m/s)c offset = offset from plume centerline (m)c xmax = maximum distance to plot or calculate to (m)c imax = distance intervalsc ymax = maximum offset to plot (m)c jmax = offset intervalsc xqmin = minimum scaled X/Q. to calculatec power = exponent in power function step size0 100 0

B4-13


4.8.3 GENII Input File

######################### Program GENII Input File ############ 8 Jul 88 ####Title: PRTR Graphite Cask - 300 Area Onsite - Inhalation & Submersion

\SAMPL\G-AIR.AC Created on 01-22-1990 at 07:30OPTIONS = = = = = = = = = = = = = = = = = = = = = = = = = Default

F Near-field scenario? (Far-field) NEAR-FIELD: narrowly-focusedF Population dose? (Individual) release, single siteT Acute release? (Chronic) FAR-FIELD: wide-scale release.

Maximum Individual data set used multiple sitesComplete Complete

TRANSPORT OPTIONS = = = = = = = = = = = = Section EXPOSURE PATHWAY OPTIONS = = = = = SetT Air Transport 1 F Finite plume, external 5F Surface Water Transport 2 T Infinite plume, external 5F Biotic Transport (near-field) 3,4 F Ground, external 5F Waste Form Degradation (near) 3,4 F Recreation, external 5

T Inhalation uptake 5,6REPORT OPTIONS = = = = = = = = = = = = = = = = = = = = = = = F Drinking water ingestion 7,8T Report AEDE only F Aquatic foods ingestion 7,8F Report by radionuclide F Terrestrial foods ingestion 7,9F Report by exposure pathway F Animal product ingestion 7,10F Debug report on screen F Inadvertent soil ingestion

INVENTORY M##UUU#U###################8#1t##1t1t1t#######U##UU1tUU##########1t##1t####

4 Inventory input activity units: (1-pCi 2-uCi 3-mCi 4-Ci 5-Bq)0 Surface soil source units (1- m2- 2- m3 3- kg)

Equilibrium question goes here

| -—Release Terms 1 -—Basic Concentrations [Use when | transport selected | near-field scenario, optionally j

I i iRelease j Surface Buried | Surface Deep Ground Surface]Radio- [Air Water Waste |Air Soil Soil Water Water |nuclide |/yr /yr /m3 |/m3 /unit /m3 /L /L |

I I ISR90 3.75E-01Y 90 3.75E-01FE59 5.00E-03PU239 1.09E-02

| —Derived Concentrations 1Use when | measured values are known |

I ' Ii I

Release |Terres. Animal Drink Aquatic|Radio- | Plant Product Water Food |nuclide |/kg /kg /L /kg |

I I

1 Intake ends after (yr)50 Dose calc. ends after (yr)1 Release ends after (yr)0 No. of years of air deposition prior to the intake period0 No. of years of irrigation water deposition prior to the intake period

FAR-FIELD SCENARIOS (IF POPULATION DOSE) #####################################

0 Definition option: 1-Use population grid in file POP.IN

0 2-Use total entered on this line

NEAR-FIELD SCENARIOS #########################################################

Prior to the beginning of the intake period: (yr)0 When was the inventory disposed? (Package degradation starts)0 When was LOIC? (Biotic transport starts)0 Fraction of roots in upper soil (top 1 5 cm)

B4-14


0 Fraction of roots in deep soil0 Manual redistribution: deep soil/surface soil dilution factor0 Source area for external dose modification factor (m2)

TRANSPORT ####################################################################

= = = =AIRTRANSPORT= = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = =SECTION

O-Calculate PM |0 Release type (0-3)3 Option: 1-Use chi/Q or PM value |F Stack release (T/F)

2-Select Ml dist & dir |0 Stack height (m)3-Specify Ml dist & dir 10 Stack flow (m3/sec)

1 Chi/Q or PM value |0 Stack radius (m)14 Ml sector index (1 =S) JO Effluent temp. (C)100. Ml distance from release point (m)]0 Building x-section (m2)T Use jf data, (T/F) else chi/Q gridjO Building height (m)

= = = =SURFACE WATER TRANSPORT= = = = = = = = = = = = = = = = = = = = = = = = = = = = = = =SECTION2 = = = = =0 Mixing ratio model: 0-use value, 1-river, 2-lake0 Mixing ratio, dimensionless0 Average river flow rate for: MIXFLG=0 (m3/s), MIXFLG = 1,2 (m/s),

. 0 Transit time to irrigation withdraw! location (hr)If mixing ratio model > 0:

0 Rate of effluent discharge to receiving water body (m3/s)0 Longshore distance from release point to usage location (m)0 Offshore distance to the water intake (m)0 Average water depth in surface water body (m)0 Average river width (m), MIXFLG = 1 only0 Depth of effluent discharge point to surface water (m), lake only

= = = =WASTE FORM AVAILABILITY = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = =SECTION3 = = = = =0 Waste form/package half life, (yr)0 Waste thickness, (m)0 Depth of soil overburden, m

= = = =BIOTIC TRANSPORT OF BURIED SOURCE= = = = = = = = = = = = = = = =SECTION 4= = = = =T Consider during inventory decay/buildup period (T/F)?T Consider during intake period (T/F)? | 1-Arid non agricultural0 Pre-lntake site condition | 2-Humid non agricultural

| 3-Agricultural

EXPOSURE #####################################################################

= = = =EXTERNAL EXPOSURE = = = = = = = = = = = = = = = = = = = = = = = = = = = = = =SECTION 5 = = = = =Exposure time: | Residential irrigation:

0 Plume (hr) | T Consider: (T/F)0 Soil contamination (hr) | 0 Source: 1-ground water0 Swimming (hr) | 2-surface water0 Boating (hr) | 0 Application rate (in/yr)0 Shoreline activities (hr) | 0 Duration (mo/yr)0 Shoreline type: (1-river, 2-lake, 3-ocean, 4-tidal basin)0 Transit time for release to reach aquatic recreation (hr)1.0 Average fraction of time submersed in acute cloud (hr/person hr)

= = = = INHALATION = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = = SECTION6 = = = = =8766.0 Hours of exposure to contamination per year0 0-No resus- 1-Use Mass Loading 2-Use Anspaugh model0 pension Mass loading factor (g/m3) Top soil available (cm)

= = = =INGESTION POPULATION= = = = = = = = = = = = = = = = =0 Atmospheric production definition (select option):0 0-Use food-weighted chi/Q, (food-sec/m3), enter value on this line

•1-Use population-weighted chi/Q2-Use uniform production3-Use chi/Q and production grids (PRODUCTION will be overridden)

0 Population ingesting aquatic foods, 0 defaults to total (person)

B4-1 5


0 Population ingesting drinking water, 0 defaults to total (person)F Consider dose from food exported out of region (default = F)

Note below: S* or Source: O-none, 1-ground water, 2-surface water3-Derived concentration entered above

= = = = AQUATIC FOODS / DRINKING WATER INQESTION= = = = = = = = =SECTION 8 = = = =

F Salt water? (default is freshl

USE TRAN- PROD- -CONSUMPTION- |? FOOD SIT UCTION HOLDUP RATE |T/F TYPE hr kg/yr da kg/yr | DRINKINQ WATER

F FISH 0.00 0.0E + 00 0.00 0.0 | 0 Source (see above)F MOLLUS 0.00 0.0E + 00 0.00 0.0 | T Treatment? T/FF CRUSTA 0.00 O.OE + 00 0.00 0.0 | 0 Holdup/transitlda)F PLANTS 0.00 O.OE + 00 0.00 0.0 | 0 Consumption (L/yr)

= = = =TERRESTRIAL FOOD INQESTION= = = = = = = = = = = = = = = = = = = = = = =SECTION 9 =

USE QROW -IRRIGATION- PROD- -CONSUMPTION-? FOOD TIME S RATE TIME YIELD UCTION HOLDUP RATET/F TYPE da * in/yr mo/yr kg/m2 kg/yr da kg/yr

. F LEAFV 0.00 0 0.0 0.0 0.0 O.OE + 00 0.0 0.0F ROOTV 0.00 0 0.0 0.0 0.0 O.OE + 00 0.0 0.0F FRUIT 0.00 0 0.0 0.0 0.0 O.OE + 00 0.0 0.0F GRAIN 0.00 0 0.0 0.0 0.0 O.OE + 00 0.0 0.0

= = = =ANIMAL PRODUCTION CONSUMPTION = = = = = = = = = = = = = = = = = = = = SECTION 10= = = =

—HUMAN—- TOTAL DRINK STORED FEEDUSE CONSUMPTION PROD- WATER DIET GROW -IRRIGATION- STOR-? FOOD RATE HOLDUP UCTION CONTAM FRAC- TIME S RATE TIME YIELD AGET/F TYPE kg/yr da kg/yr FRACT. TION da * in/yr mo/yr kg/m3 da

F BEEF 0.0 0.0 0.00 0.00 0.00 0.0 0 0.0 0.00 0.00 0.0F POULTR 0.0 0.0 0.00 0.00 0.00 0.0 0 0.0 0.00 0.00 0.0F MILK 0.0 0.0 0.00 0.00 0.00 0.0 0 0.0 0.00 0.00 0.0F EGG 0.0 0.0 0.00 0.00 0.00 0.0 0 0.0 0.00 0.00 0.0

FRESH FORAGEBEEF 0.00 0.0 0 0.0 0.00 0.00 0.0MILK 0.00 0.0 0 0.0 0.00 0.00 0.0

B4-16


4.8.4 Checklist for Technical Peer Review

CHECKLIST FOR REVIEW

Document Reviewed: THI for the 327 Building Family of Casks

Scope of Review: entire document

Yes No NA[ ] [ ] M *

M EY\ [:•"•] t

A [yi i

] t ]3 t :] [ :i [:3 t :] c ]

H [ 3 [ 3

[<f [ 3 [ 3

M [ 3 [ 3

M [ ] C 3M [ ] [ ]M I 3 [ 3

M 3 [ 33 [•]

W [ 3 [ 3

MUM[ 3 [*}.

M [ 1 I 1

Previous reviews complete and cover analysis, up to scope ofthis review, with no gaps.Problem completely defined.Accident scenarios developed in a clear and logical manner.Necessary assumptions explicitly stated and supported.Computer codes and data files documented.Data used in calculations explicitly stated in document.Data checked for consistency with original source informationas applicable.Mathematical derivations checked including dimensionalconsistency of results. • .Models appropriate and used within range of validity or useoutside range of established validity justified.Hand calculations checked for errors. Spreadsheet resultsshould be treated exactly the same as hand calculations.Software input correct and consistent with document reviewed.Software output consistent with input and with resultsreported in document reviewed.Limits/criteria/guidelines applied to analysis results areappropriate and referenced. Limits/criteria/guidelinss 'checked against references.Safety margins consistent with good engineering practices.Conclusions consistent with analytical results and applicablelimits. . ' . 'Results and conclusions address all points required in theproblem statement.Format consistent with appropriate NRC Regulatory Guide orother standardsReview calculations, comments, and/or notes are attached.

Document approved.

J. G. McFaddenReviewer (Printed Name and Sigfiajture) / Date

* Any calculations, comments, or notes generated as part of this review shouldbe signed, dated and attached to this checklist. Such material should belabeled and recorded in such a manner as to be intelligible to a technicallyqualified third party.

B4-17


4.8.5 HEDOP Review Checklist

HEDOP REVIEW CHECKLISTfor

Radiological and Konradiological Release Calculations

Document: Transportation Hazard Index (THI) Analysis for the 327 BuildingCasks SEPs," Hay 9, 1997.

Scope of Review: Inhalation/Air Submersion Dose Calculations

YES NO* N/A

[x] [ ] [ ] 1. A detailed technical review and approval of theenvironmental transport and dose calculation portion ofthe analysis has been performed and documented.

[ ] [ ] [x] 2. Detailed technical review(s) and approval(s) of scenarioand release determinations have been performed anddocumented.

[ ] [x] [ ] 3. HEDOP-approved code(s) were used,[x] [ ] [ ] 4. Receptor locations were selected according to HEDOP

recommendations,[x] [ ] [ ] 5. All applicable environmental pathways and code options

were included and are appropriate for the calculations,[x] [ ] [ ] 6.- Hanford site data were used.[x] [ ] [ ] 7. Model adjustments external to the computer program were

justified and performed correctly.[x] [ ] [ ] .8. . The analysis is consistent with HEDOP recommendations.[x] [ ] 9. Supporting notes, calculations, comments, comment

resolutions, or other information is attached. (Use the"Page 1 of X" page numbering format and sign and dateeach added page.)

[x] [ ] 10. Approval is granted on behalf of the HanfordEnvironmental Dose Overview Panel.

* All "NO" responses must be explained and use of nonstandard methodsjustified.

Kathv RhoadsHEDOP-Approved Reviewer (Printed Name and Signature) . Date

COMMENTS (add additional signed and dated pages if necessary):

Item 3: GXQ used for air transport calculations; GENII results are includedfor comparison.

19

B4-18


5.0 SHIELDING EVALUATION

5.1 INTRODUCTION

This shielding evaluation supports the shipment of activated materials and fuel components inthe PRTR Graphite Cask within the Hanford 300 Area.

5.2 DIRECT RADIATION SOURCE SPECIFICATION

The source term for the materials transported by the cask will be variable and, therefore, isdescribed generally and evaluated on the basis of bounding conditions for gamma and neutronemissions. The source term evaluated for shielding is shown in Table B5-1. Isotopes other than thoselisted may be shipped in the cask, but the surface dose rate is limited to those shown in Part B,Section 5.4, in all cases.

Table B5-1. Maximum Allowable Shielding Source Term.

Material

Fissile materials and aemitters*



Activity limit

TBq

0.401

13.9

0.185

Ci

10.9

375

5.00

Comments

a-emitting materials, except for 175 g (10.85 Ci)239Pu, were not considered for shielding. Theneutron dose rate from 239Pu bounds the neutrondose rate for all other materials in this category.

Considered to be all 137Cs for shielding

Considered to be all 60Co for shielding

* Fissile/fissionable materials limited by criticaiity safety as shown in Part B, Section 2.1.1.

5.2.1 Gamma Source

The gamma source term evaluated is a mixed inventory of 60Co and 137Cs with an equilibriumamount of the 137Cs daughter, 137mBa. Although the mixed inventory may have additional gammasources, these are bounded by the 60Co and 137Cs terms and were not considered separately.

5.2.2 Beta Source

Beta particles originating in the source do not contribute directly to the dose rate outside thecasks because of the shielding provided. Although the bremsstrahlung radiation produced by thedeceleration of the beta particles in the source is a potential contribution to the source, the contributionis minimal and bounded by the gamma source term discussed in Part B, Section 5.1.2. For the isotopesevaluated, however, bremsstrahlung was considered.

5.2.3 Neutron Source

The neutron source term for the mixed materials inventory was calculated using the ORIGEN2(Schmittroth 1994) computer code. The worst-case neutron source term was found to be from 239Pu

B5-1


and was found to occur prior to any decay being considered. Although 235U was considered, theneutron source term is negligible compared to 239Pu. The source term is shown in Table B5-2, and theORIGEN2 input file is included in Part B, Section 5.8.

Table B5-2. Neutron Source Term for 175g of 239Pu

Component of source

(a,n)

Spontaneous fission

Total

Source strength (neutrons/s)

7.927 E+03

3.967

7.931 E + 03

The cesium capsule inventory has no neutron emitters.

5.3 SUMMARY OF SHIELDING PROPERTIES OF MATERIALS

The shielding in the PRTR Graphite Cask is provided by lead encased in a stainless steel shell.The default densities for iron and lead provided in the ISO-PC (Rittmann 1995) computer code wereused for shielding calculations.



Gamma dose rates were evaluated at the surface of the cask (with an offset of 1.0 cm) and at2.0 m (6.6 ft) from the cask surface. Neutron dose rates were estimated at the surface of the cask.

5.4.2 Acceptance Criteria

Transportation safety specifies a maximum of 2 mSv/h (200 mrem/h) on any surface of thecask, 0.1 mSv/h (10 mrem/h) at 2.0 m (6.6 ft) from the cask surface, and 0.02 mSv/h (2 mrem/h) inany normally occupied space. If these limits are exceeded, material will be removed from the cask.

5.4.3 Assumptions

The following assumptions were made and applied to the shielding model.

1. The steel in the closure mechanism tube was combined with the steel covering theoutside of the mechanism to make a single inner shell and outer shell.

2. The air space in the closure mechanism was added to the distance to the detector.

3. The cask end opposite the closure contains a steel plunger mechanism that extendsthrough the shielding (see drawing H-3-13699 [Part A, Section 10.1]). A cylindricalsource with a diameter equivalent to the plunger mechanism and a length equivalent tothe cask cavity was used to determine the dose outside the plunger. This dose was

B5-2


added to the dose considered at the cask end, assuming a uniform steel and lead plugwithout the plunger. It is assumed that the cask is transported with the sample boat inplace and that a steel rod fills the hole through the plunger mechanism.

4. The contents were assumed to be mainly iron pieces with a nominal density of2.0 g/cm3. This density was arrived at by considering that the cask is filled withuniformly distributed iron pieces with a density approximately one-fourth of the nominaliron density of 7.86 g/cm3. Note that dose rates are more sensitive to material densitythan material type; therefore, this is a conservative approach that reduces the effectsof self-shielding in the payload.

5. The mixed activation products were conservatively assumed to be all 60Co.

6. The mixed fission products were conservatively assumed to be all 137Cs.

7. Bremsstrahlung was only considered for isotopes evaluated; e.g., 137Cs, and not for anyother isotopes that may be present, such as 90Sr.

5.4.4 Shielding Model

The shielding source term considered is shown in Tables B5-1 and B5-2. The sourceparameters are shown in Table B5-3, and the shielding parameters are shown in Table B5-4. The datafor the shielding and source parameters were taken from drawing H-3-13699.

Table B5-3. Source Parameters.

Source

Overall (entire cask interior volume)

Plunger only (part of source directlybelow plunger area)

Diameter

cm

7.938

3.334

in.

3.125

1.3125

Length

cm

62.2

62.2

in.

24.49

24.49

Volume(cm3)

3082.300

543.718

Table B5-4. Shielding Parameters.

Detectorlocation

Side

Closure end

Plunger end

Plunger

Steel inner wallthickness

cm

0.318

0.953

1.905

in'.

0.125

0.375

0.750

Diameter

cm

3.334

in.

1.3125

Lead thickness

cm

12.860

10.133

12.065

in.

5.063

3.989

4.750

Length

cm

14.923

in.

5.875

Steel outer wallthickness

cm

0.635

0.953

0.953

in.

0.250

0.375

0.375

Distance to surfacedetector (Includingsource thickness)

cm

17.781

83.796

77.127

in.

7.001

32.990

30.365

B5-3


The ISO-PC program (Rittmann 1995} was used for the gamma-ray dose rate calculations.ISO-PC uses the point-kernel integration method to compute the dose rate at a detector location.Bremsstrahlung photons are accounted for in the dose rate calculations. Fluence-to-dose conversionfactors were based on an anterior-to-posterior irradiation pattern (ANS 1991).

The neutron dose rate was determined using a method discussed in Estimation of Neutron DoseRates from Nuclear Waste Packages {Nelson 1996). This is a very conservative method that does nottake shielding or moderation into account.

5.4.5 Shielding Calculations

Table B5-5 shows the gamma dose, rate estimates calculated by ISO-PC for the mixed materialinventory. The neutron dose rate calculations utilized data for a,n and spontaneous fission neutronproduction rates generated by ORIGEN. The neutron production rate information was then used in thedose rate calculation method described in Estimation of Neutron Dose Rates from Nuclear WastePackages (Nelson 1996). The neutron dose rate was determined to be 0.0125 mSv/h (1.25 mrem/h) atthe cask surface. The neutron dose rate falls of by a factor of 1/r2 and is negligible at 2.0 m (6.6 ft).The ISO-PC input file, the ORIGEN input file, and the neutron dose calculations are attached in Part B,Section 5.8.

Table B5-5. Maximum Dose Rates Around the PlutoniumRecycle Test Reactor Graphite Cask.

Detector orientation

Side (gamma and neutron)

Closure end {gamma only)

Plunger end plus plunger {gamma only)

Criteria

Detector location

Surface (1cm offset)

mSv/h .

1.09

1.87

1.94

2.00

mrem/h

108.65

187.00

194.21

200.00

2 m

mSv/h

3.20 E-03

3.20 E-03

1.79 E-02

1.00 E-01

mrem/h

0.32

0.32

1.79

10.00

5.5 ACCIDENT CONDITIONS


A handling accident in which the source material was concentrated against the plunger end ofthe cask was considered.


The maximum dose rate at 1.0 m (3.3 ft) shall be less than 10 mSv/h (1,000 mrem/h).

B5-4


5.5.3 Assumptions

The same assumptions as shown in Part B, Section 5.4.3, shall be used except that the sourcematerial will be concentrated in a cylinder that is the same diameter as the cask interior and 5.08 cm(2.0 in.) tall. The material density will be conservatively maintained as 2.0 g/cm3.

5.5.4 Shielding Model

The shielding model shall be the same as used in Part B, Section 5.4.4, except that the sourcelength will 5.08 cm (2.0 in.).

5.5.5 Shielding Calculations

Table B5-6 shows the gamma dose rate estimates for accident conditions as oalcuiated byISO-PC (Rittmann 1995). The neutron dose rate was not calculated as it is was already shown to beinsignificant when compared to the gamma dose rate, even without shielding, in Part B, Section 5.4.The ISO-PC input file is attached in Part B, Section 5.8.

Table B5-6. Maximum Dose Rates Around the Plutonium RecycleTest Reactor Graphite Cask for Accident Conditions.

Detector orientation

Side

Closure end

Plunger end plus plunger

Detector location (1 m)

mSWh

1.11 E-02

2.50 E-02

3.62 E-01

mrem/h

1.11

2.50

36.17

5.6 CONCLUSIONS

The gamma dose rates shown in Table B5-5 for the mixed materials inventory are within theNTC acceptance criteria for a surface dose rate of less than 2 mSv/h (200 mrem/h), 0.1 mSv/h(10 mrem/h) at 2.0 m (6.6 ft), and 0.02 mSv/h (2 mrem/h) at the driver's position, assuming the driveris no closer to the cask than 2.5 m. As shown in Table B5-6, the maximum allowed accident conditiondose rate is also met for the conditions evaluated. The neutron dose rate of 0.0125 mSv/h(1.25 mrem/h) at the cask surface is inconsequential for the material inventory considered as it falls offby a factor of 1/r2 and is negligible in comparison to the gamma dose rate.

It should be noted that the shielding model is very conservative, assuming a contents density of2.0 g/cm3 that is evenly distributed in the cask volume and assuming that the activated materialsinventory is all 60Co. During use, the dose rates are measured prior to shipment in accordance withfacility procedures. Particular attention must be paid to the plunger end of the cask due to the reducedshielding-in this area. If the dose rate on any surface exceeds the NTC requirements, payload materialwill be removed in order to meet the dose rate limits.

B5-5


5.7 REFERENCES

ANS, 1991, Neutron and Gamma-Ray Fluence-to-Dose Factors, ANSI/ANS-6.1.1-1991, AmericanNuclear Society, La Grange Park, Illinois.

Nelson, J. V., 1996, Estimation of Neutron Dose Rates from Nuclear Waste Packages, (internal memo8M730-JVN-96-007 to J. R. Green, March 8), Westinghouse Hanford Company, Richland,Washington.

Rittmann, P. D., 1995, ISO-PC Version 1.98 - User's Guide, WHC-SD-WM-UM-030, Rev. 0,Westinghouse Hanford Company, Richland, Washington.

Schmittroth, F. A., 1994, Conversion of 0RIGEN2 to Sun Workstations, WHC-SD-NR-SWD-00, Rev. 1,Westinghouse Hanford Company, Richland, Washington.

5.8 APPENDICES

5.8.1 ISO-PC Input Files

0 2 PRTR CaskCase Side

&lnputNext = 1, IPrnt=O, IGeom = 7, ICONC = O, SFACT=1,DUNIT=1, NTheta= 30, NPsi= 30, NShld= 4, JBuf= 3, OPTION = 0,Slth= 62.2,T(1|= 3.969,T(2)= 0.318,T(3)= 12.860,T[4)= 0.635,X= 18.782,Y= 31.1,WEIGHTI335) = 375.0 ,WEIGHTI336) = 354.75 ,WEIGHTI472) = 5.0, &Steel 9 2.0Steel 9 7.86Lead 14 11.351 Steel 9 7.86Dose Rate at 2 m&lnput Next = 4, X = 217.782, &Case Closure End

&lnputNext= 1, IPrnt = O, IGeom = 9, ICONC=O, SFACT=1,DUNIT= 1, NTheta= 30, NPsi= 30, NShld= 4, JBuf= 3, OPTION = 0,Slth= 3.969,T(1)= 62.2,TI2)= 0.953,T(3)= 10.133,T(4)= 0.953,X= 84.796,WEIGHTI335) = 375.0 ,WEIGHTI336) = 354.75 ,WEIGHTI472) = 5.0, &Steel 9 2.0Steel 9 7.86Lead 14 11.351 Steel 9 7.86Dose Rate at 2 m&lnput Next = 4, X = 283.796, &Case Plunger End

&lnput Next= 1, IPrnt = O, IGeom= 9, ICONC = 0, SFACT=1,DUN1T= 1, NTheta= 30, NPsi= 30, NShld= 4, JBuf= 3, OPTION = 0,Slth= 3.969,T(1)= 62.2,

B5-6


T(2)= 1.S05,T(3)= 12.065,T(4)= 0.953,X= 78.127,WEIGHTI335) = 375.0 ,WEIGHTI336) = 354.75 ,WEIGHT(472) = 5.0, &Steel 9 2.0Steel 9 7.86Lead 14 11.351 Steel 9 7.86Dose Rate at 2 m&lnput Next = 4, X = 277.127, &Estimate Driver Position (2 m)&lnput Next=4, X = 277.127, &Case Plunger

&lnput Next = 1, IPrnt = O, IQeom= 9, ICONC = 0, SFACT= 0.176,DUNIT= 1, NTheta= 30, NPsi= 30, NShld= 2, JBuf= 2, OPTION = 0,Slth= 1.667,T(1)= 62.2,T(2I= 14.923,X= 78.123,WEIGHTI335) = 375.0 ,WEIGHTI336) = 354.75 ,WEIGHTI472) = 5.0, &Steel 9 2.01 Steel 9 7.86Dose Rate at 2 m&lnput Next=4, X = 277.123, &Estimate Driver Position {2 m}&lnputNext=4, X = 277.123, &Case Side Accident

&lnput Next= 1, IPrnt = O, IGeom = 7, ICONC = 0, SFACT=1,DUNIT = 1, NTheta = 30, NPsi = 30, NShld = 4, JBuf = 3, OPTION = 0,Slth= 5.08,T(1)= 3.969,T(2)= 0.318,T(3)= 12.860,T(4)= 0.635,X= 118.782,Y= 31.1,WEIGHTI335) = 375.0 ,WEIGHTI336I = 354.75 ,WEIGHT(472) = 5.0, &Steel 9 2.0Steel 9 7.86Lead 14 11.351 Steel 9 7.86Case Closure End Accident

&lnput Next= 1, IPrnt = O, IGeom= 9, ICONC = 0, SFACT=1,DUNIT = 1, NTheta = 30, NPsi= 30, NShld = 5, JBuf= 4, OPTION = 0,Slth= 3.969,T(1)= 5.08,T(2>= 57.12,T(3)= 0.953,T(4)= 10.133,T(5)= 0.953,X= 184.796,WEIGHT(335I = 375.0 ,WEIGHTI336I = 354.75 ,WEIGHTI472) = 5.0, &Steel 9 2.0Air 3 0.00129Steel 9 7.86Lead 14 11.351 Steel 9 . 7.86Case Plunger End Accident

&lnput Next= 1, IPrnt = O, IGeom= 9, ICONC = 0, SFACT=1,DUNIT = 1, NTheta = 30, NPsi= 30, NShld = 4, JBuf= 3, OPTION = 0,

B5-7


Slth= 3.969,T(1)= 5.08,T(2)= 1.905,T(3)= 12.065,T(4)= 0.953,X= 121.003,WEIGHTO35) = 375.0 ,WEIGNTI336) = 354.75 ,WEIGHT(472> = 5.0, &Steel 9 2.0Steel 9 7.86Lead 14 11.351 Steel 9 7.86Case Plunger Accident

Silnput Next= 1, IPrnt=0, IGeom= 9, IC0NC=0, SFACT= 0.176,DUNIT= 1, NTheta= 30, NPsi= 30, NShld = 2, JBuf= 2, OPTION=O,Slth= 1.667,T(1)= 5.08,T(2)= 14.923;X= 121.003,WEIGHTI335) = 375.0 ,WEIGHTI336) = 354.75 ,WEIGHTI472) = 5.0, &Steel 9 2.01 Steel 9 7.86End of InputStlnput Next= 6 &

5.8.2 ORIGEN Input File

-1-1TIT PU DECAY - 175 g Pu239/ 275 g U235 - Neutron Emission Calc8AS PLUTONIUM DECAY IN 5 YEAR INTERVALSLIP 0 0 0LIB 0 1 2 3 381 382 383 9 0 0 1 1 .PHO 101 102 103 10RDA 1 METRIC TON PLUTONIUMINP - 1 1 - 1 - 1 1 1RDA DECAY FUELMOV -1 1 0 1.00RDADEC 50.0 1 2 4 0DEC 1.0 2 3 5 0DEC 10.0 3 4 5 0DEC 20.0 4 5 5 0DEC 30.0 5 6 5 0DEC 40.0 6 7 5 0DEC 50.0 7 8 5 0DEC 60.0 8 9 5 0DEC 70.0 9 10 5 0DEC 80.0 10 11 5 0RDACUT 5 1.6-10 7 1.E-10 9 1.E-10 -1OPTL 2 4 ' 8OPTF 24"8OPTA 4"8 7 7 7 8 7 8 14*8OUT 1 1 1 - 1 0STP 42 942390 175.000 922350 275.00 0 0 0 00END

B5-8


5.8.3 Neutron Dose Calculations

The neutron dose rate was determined using, the method described in Estimation of NeutronDose Rates from Nuclear Waste Packages {Nelson 1996). In this method, the total neutron sourceterm SIT), which accounts for neutron multiplication, is determined by adding the spontaneous fissionsource term (S(SF)) and the cc,n source term (S( a,n)} and dividing by 1 minus the keff.

= (S{SF) - S(g, n))(1 * )

S(SFI and S( a,n) are determined either from Nelson (1996) or ORIGEN (see Part B, Section 5.8.2).After S(ST) is determined, it is used to determine the dose rate in the equation;

D(r) __ 0.01 • S(ST)

where r is the distance from the source and D(r) is the dose in mrem/h as a function of r.

Therefore, the neutron dose for the PRTR Graphite Cask is estimated as follows. Using S(SF)and S( a,n) from ORIGEN and conservatively assuming a kell of 0.8 (Part B, Section 6.0), S(ST) isdetermined to be,

3.967 • 7.927 x 10*(1 - 0.8)

Assuming r to be 17.78 cm (the approximate surface of cask as measured radially), the total neutrondose rate is estimated to be,

D(r) = 0.01 • 3.965 X 10< = ,h17.782

B5-9


5.8.4 Peer Review Checklist for Shielding

CHECKLIST FOR TECHNICAL PEER REVIEW

Document: Safety Evaluation for Packaging (Onsite) PRTR Cask, June 4, 1997,by John McCoy.

Scope: Shielding portion of the analysis.

Yes No NA[ ] [ ] [X] Previous reviews complete and cover analysis, up to scope of

this review, with no gaps.[X] [ ] [ ] Problem completely defined.[ ] [ ] [X] Accident scenarios developed in a clear and logical manner.[X] [ ] [ 1 Necessary assumptions explicitly stated and supported.[X] [ ] [ ] Computer codes and data files documented.[X] [ ] [ ] Data used in calculations explicitly stated in document.[X] [ ] £ ] Data checked for consistency with original source information

as applicable.[X] [ ] [ ] Mathematical derivations checked including dimensional

consistency of results.[X] [ ] [ ] Models appropriate and used within range of validity or use

outside range of established validity justified.[X] [ ] [ ] Hand calculations checked for errors. Spreadsheet results

should be treated exactly the same as hand calculations.[X] [ ] [ ] Software input correct and consistent with document reviewed.[X] [ ] [ ] Software output consistent with input and with results

reported in document reviewed.[X] [ ] [ ] Limits/criteria/guidelines applied to analysis results are

appropriate and referenced. Limits/criteria/guidelineschecked against references.

[X] [ ] [ ] Safety margins consistent with good engineering practices.[X] [ ] [ ] Conclusions consistent with analytical results and applicable

limits.[X] [ ] [ ] Results and conclusions address all points required in the

problem statement.[X] [ ] [ ] Format consistent with appropriate NRC Regulatory Guide or

other standards[ ] [X] Review calculations, comments, and/or notes are attached.

[X] [ ] [ ] Document approved.

Anthony Saving MJj*—± : 6/ 4/97Reviewer (Printed Name and Signature) . Date

B5-1O


6.0 CRITICALITY EVALUATION

The criticality analysis of the PRTR Graphite Cask was completed in Limits for FissionableMaterial, in Small Bore Transfer Casks and Lead Pigs (see Section 6.1). This analysis demonstrates thatthe PRTR Graphite Cask remains subcritical when loaded with 275 g or less of 23BU. The package isalso subcritical when loaded wi th 175 g or less of 239Pu, 2 3 3U, 237Np, 2 4 'Am, 243Am, w C m , and 247Cm.The following fissionable materials were not analyzed and cannot be shipped in excess of safeguardsaccountability limits: M 2 " A m , 243Cm, 245Cm, M9Cf, or 251Cf.

6.1 APPENDIX: CRITICALITY SAFETY ANALYSIS

B6-1


llBatfenePacific Northwest Laboratories

Date December 30, 1996

To M Dec

From SL Larson <yC- Ussw-

subject NCS Basis Memo 96-2. Limits for FissionableMaterial in Small Bore Transfer Casks and LeadPigs

Internal Distribution

VC AsmundAL DohertyDL HaggardAWPrichardRD ScheeleLibraryRecord CopyFile/LB

Reference 1: PNL Laboratory Safety, "Criticality Safety," PNL-MA-25, January 1994.

Reference 2: Oak Ridge National Laboratory, SCALE 4.2 Modular Code System for PerformingStandardized Computer Analyses for Licensing Evaluation, vl-3, CCC-545, November1993.

Reference 3: SL Larson, "A Systematic Approach to Establishing Criticality Biases," Proceedings ofthe International Conference on Nuclear Criticality 1995, Albuquerque, NM, September17-21,1995.

Reference 4: LE Hansen, ED Clayton, RC Lloyd, SR Bierman and RD Johnson, "Critical Parametersof Plutonium Solutions," Parts I and II, Nuclear Applications, & 371-390,1969.

Reference 5: BM Durst, SR Bierman and ED Clayton, "Handbook of Critical ExperimentsBenchmarks," PNL-2700, March 1978. .

Reference 6: RC Lloyd, CR Richey, ED Clayton, and DR Skeen, "Criticality Studies with PlutoniumSolutions," Nuclear Science and Engineering, vol 25, pp 165-173, 1966.

Reference 7: NEA Nuclear Science Committee, International Handbook of Evaluated CriticalitvSafety Benchmark Experiments. Experiment HEU-MET-FAST-004,NEA/MSC/DOC(95)03/II, 1995.

Reference 8: SR Bierman, BM Durst and ED Clayton, "Critical Experiments with Subcritical Clustersof 2.35 \vt% and 4.31 wt% 235U Enriched UO2 Rods in Water with Uranium or LeadReflecting Walls," NUREG/CR-0796, vol 2, 1979.

This basis memo establishes the nuclear criticality safety limits for the loading, unloading, storage andon-site transportation of fissionable material in the following casks: the Large Bore Cask, the Long BoreCask, the PRTR Graphite Cask and the One Ton Cask and any other lead shielded cask with a maximuminner volume of 5 liters. This memo validates the limits against the requirements of DOE Order 54S0.24issued 8/12/92 and ANSI/ANS-8.1-19S3 [Reaffirmed 1988].

B6-2


NCS Basis Memo 96-2December 30,1996Page 2

Review of Methods Used Previously

The mass limits for water reflected fissionable material were previously used for the transfer casks. Thecasks were not specifically analyzed previously. However, calculations have shown that the lead usedfor shielding may be a better reflector than water thereby possibly reducing the minimum critical mass.

Validation of the Technical Rases per ANSI/ANS-8.1 -1983 [1988] Requirements

An analysis was conducted per the requirements of ANSI/ANS-8.1-1983 [Reaffirmed 1988]. The resultsare as follows:

(1) Describe the method with sufficient detail, clarity, and lack of ambiguity to allowindependent duplication of results.

The transfer casks analyzed in this memo have a small inner bore which limits the contents.Because a large number of fuel pins can not fit into the casks, a mass limit but not a pin limitwas determined for the casks. Fuel pins and pieces can be transported and stored in the casksunder the mass limit.

(1.1) Optimum Concentration Determination >r-

The first step in analyzing the lead shielded casks was to determine the optimum concentration ofan aqueous spherical solution of fissile material with a tight fitting spherical lead reflector. Themass of material modeled is equal to a double batch under the current water reflected limits forthese materials. A lead reflector thickness of 8" was chosen because.the casks have a comparablelead thickness. The results as given in Table 1 indicate that the optimum fissile concentrationswith lead reflection are 32 g/1 for MPu and 55 g/1 for !35U. These values are comparable to theoptimum water reflected concentrations found in previous work. A K$slis value was notcalculated as these calculations are for comparison only. However, notice the systems aresupercritical with a lead reflector although the mass is less than the minimum critical waterreflected mass (530 g 23sPu or 738 g 23iU). This point indicates that lead is a significantly betterreflector than water for an aqueous solution system of 239Pu or 235U.

^ / * ^?

Table 1 Optimum Fissile Concentration with. Lead Reflection

Case"

460 g sphere460 g sphere460 g sphere460 g sphere

Fissile density (g/1) K E N O k ^ ,

"•Pu Scrap27323742

1.0522ULoseio'1"*'"1.051521.04596

KENO Uncertainty

0.00114.0.00113 "•'•'"'0.001130.00150

B6-3



Table 1 Optimum Fissile Concentration with Lead Reflectioni i

C a s e ; . j Fissile density (g/1) j KENO ktflicIivc KENO Uncertainty

'"UScrap738 g sphere | 45

738 g sphere ' 501.04042 i 0.001231.04452

738 g sphere j 55 j 1.04661

738 g sphere 1 60 . I 1.04492

. 0.00116

0.001200.00123

* Each case models a sphere of fissile material surrounded by an 8" tight fittingspherical lead reflector. Full water reflection was also modeled around the lead.

(1.2) Large Bore, Long Bore, PRTR Graphite and One Ton Sample Cask Analyses

The four casks specifically analyzed were the Large Bore, the Long Bore, the PRTR Graphite andthe One Ton Sample Casks. The casks were modeled using the KENO-Va code to ensuresubcriticality of the water reflected mass limit for235U and 23sPu in the cylindrical geometry of thecasks during normal operations and in the event of a single loss of contingency. The innerdiameter of the cask was increased in the KENO model by 0.4" to ailow for tolerance and createa more optimum concentration of material in the cask. The interior length of the cask wasmodeled as 1" longer than the actual length for the same reasons. Lead has a large thermalscattering cross section and small thermal absorption cross section. Therefore, the lead thicknessof the cask was also increased in the model to allow for tolerance as a thicker lead reflector ismore reactive for thermal, optimally moderated system. The actual dimensions and the asmodeled dimensions for each of the four casks modeled are given in Table 2.

Table 2 Cask Dimensions

Cask

Large Bore

Long Bore

PRTR Graphite

One Ton Sample

Nominal Dimensions

InnerDiameter

4"

• 3 "

3.25"

3"

InnerLength

26"

39"

25"

13.125"

LeadThickness

7.75"

7.5"

5.375"

6.5"

Modeled Dimensions

Inner j InnerDiameter i Length

l •

4.4" ; 27"

3.4" ! 40"

3.6" i 26"•

3.4" 14.25"

LeadThickness

8.34"

8.09"

5.96"

7.09"

B6-4



The casks were modeled with the fissionable material in a homogeneous water solution fillingthe bore. Full water reflection (>12") was included around the lead shielding to model the mostreactive reflection scenario possible. Three cases with different fissile masses and concentrationswere modeled. The first case demonstrates subcriticality in the event the mass limit is exceededwhile the latter two cases demonstrate that normal operations will have a reactivity less than thenormal operations limit of 0.95. In the first case, the minimum critical mass of material, 820 g23SU or 53 0 g 239Pu, was modeled with the concentration of the material determined by the volumeof the cask. In the second case, the cask was filled with the water reflected mass limit ofmaterial, 369 g 23iU or 230 g23'Pu, with the concentration again determined by the volume of thecask. The final case modeled the material at the optimum concentration, 55 g/1 for 2J5U or 32 g/1for239Pu, with the mass of material determined by the volume of the cask. As shown in Table 3,each case was subcritical. Note the reactivity is too low in these cases to accurately determine aKOTS value. Because the statistical analysis of the code was performed on critical benchmarks,extrapolation to these low reactivities is not possible. However, these low reactivities indicatethe systems are very subcritical with a k , ,^ , , certainly less than 0.90.

Table 3Cask

Large Bore

Water Moderated Scrap Limits in Small Bore CasksMax Cask

Diameterlin)

4:4I 4.4

Long Bore

PRTR Graphite

One Ton Sample

3.43.43.43.63.6

3.63.43.4

3.4

Large Bore

Long Bore

4.44.44.43.4

3.4

3.4

Fissiledensity (a/1)

Fissile massfel '

'"UScrap

122.255

138.362.3

55184.683.1

55391.7176.3

55

820

369820369326820369244820

369115 •

Kenok.,,.

0.78525

0.645290.615480.499880.475770.662890.562270.493080.608000.54668

• 0.39872

KenoUncertainty

0.00137

0.001120.001050.001040.001000.001270.001080.000980.001220.00125

0.00094n'Pu Scrap

7 9 •

34.332

89.438.832

530230215530230

190

0.789950.66425

0.649650.626510.517760.48584

0.001300.001070.001190.001170.00094

0.00088

B6-5



Table 3

Cask

PRTR Graphite

Dne Ton Sample

Water Moderated Scrap Limits in Small Bore CasksMax Cask

Diameter (in)

3.63.63.63.43.43.4

Fissiledensity Cs/1)

Fissile mass<s)

119.4 | 53051.832

253.2

230142530

110 ! 23032 I .67

Benchmark StatisticsBias = 0.00032

Standard Deviation = 0.01163Variance = 0.00014

Kenok rr

0.662190.571430.498190.597680.54649

0.40650

1 Keno! Uncertainty

i 0.00130' 0.00114i 0.00082 .

! 0.00121! 0.00113i 0.00093

The lead thickness of the Large Bore Cask containing 230 g of 23'Pu, the most reactive case at themass limit as given in Table 3, was increased by 4" to 28" to model a loss of reflection limitaccident. This scenario could occur if lead bricks were stacked around the cask or two caskswere placed side by side. As determined in Section 1.3,28" of lead is considered criticallyinfinite such that increasing the thickness would not increase reactivity. The keffecrive of the caskincreased to 0.73001 ± 0.00111 which is clearly still subcritical.

Note the calculations shown here indicate the water reflected limits in use at the Laboratory areappropriate for these lead shielded casks. This fact does not, however, indicate that lead is acomparable reflector to water for thermal systems. In these cases, the geometry of the caskslimits the mass and concentration such that optimum conditions can not be realized.

(1.3) Five Liter Cask Analysis

Instead of analyzing every small bore cask and lead transfer pig in use at the Laboratory, themaximum fissionable mass limit for a cask with an inner volume of 5 L and an infinite leadthickness was determined. The fissile material was modeled as a sphere surrounded by a tightfitting spherical lead reflector as this case is most reactive. A mass limit of 275 g 2!!U Or 175 g23sPu ensures the system will remain subcritical under all loss of contingency scenarios as givenin Table 4. Note 235U was not modeled with an increased volume as the normal condition resultsin an optimally moderated solution.

B6-6


NCS Basis Memo 96-2December 30, 1996Page 6

Table 4

: a s e b •

Maximum Allowable Volume with Full Lead Reflection

Cask j FissileVolume (!) j density (g/1)

Fissile mass LeadThickness

(in)

KENO KENOUncertainty

mPu Scrap •

Normal ConditionsLoss of Mass LimitLoss of Reflector Limit

Loss of Volume Limit

5 ! 35 ! 175 j 285 j 70 ! 350 : 28

5 j 357.47 . 32

175 ! 32

175 28

0.849190.934790.86916

0.88350

0.001000.00108

0.001330.00108

0.8730.986

0.8770.880

:3!U ScrapNormal ConditionsLoss of Mass LimitLoss of Reflector Limit

5 i 55 ! 275 28

5 I 110 | 550 [ 285 i 55 | 275 ! 32

0.830770.960020.83255

0.001140.001400.00117

0.8580.987

0.859* Each case models a sphere of fissile material surrounded by a tight fitting spherical lead reflector of

the indicated thickness. Full water reflection is also modeled around the lead.Benchmark Statistics

Bias = 0.00032Standard Deviation = 0.01163

Variance = 0.00014 «

Therefore the mass limit for the Large Bore, the Long Bore, the One Ton Sample Cask and thePRTR Graphite Cask as well as any lead shielded cask with a maximum inner volume of 5 L isset at 275 g 235U or 175 g 239Pu to provide consistency between the casks. The scrap limit foundfor 239Pu is applicable to all other fissionable materials with a minimum critical mass greater thanthat of 239Pu as given in Table 6.5 of Reference 1. Fissionable material more reactive than 239Pu,i.e., 242™Am, 243Cm, 24!Cm, 2<'Cf, or K1Cf have not been analyzed; however these materials areconsidered to be insignificant for the purposes of criticality safety provided the mass does notexceed the safeguards accountability limits. None of these restricted materials are currentlyaccounted for at the Pacific Northwest National Laboratory; therefore violation of this limit is notcredible. Sum of Fractions method (Ref. 1, Table 6.1) may be used to determine limitcompliance for mixtures of fissionable material.

(1.4) Spacing Requirements

The minimum 12" edge-to-edge spacing requirement for batches of fissionable material isapplicable to the transfer casks and lead pigs. Because the lead in the casks is not of an infinitethickness for criticality, material around the cask will affect the reactivity of the cask. However,the cask was proven to be subcritical with an infinite lead thickness in all directions. Therefore,the 12" edge-to-edge spacing requirement is in effect between the cask and other batches of

B6-7



fissionable material but no spacing requirements are needed between the cask and otherreflectors.

(2) State computer programs used, the options, the recipes for choosing mesh pointswhere applicable, the cross section sets, and any numerical parameters necessary todescribe the input.

The SCALE 4.2 system of codes2 was used to model the casks. The codes were executed oneither a HP 755 with HP-UNIX version 9.03 or a HP 735 running HP-UNIX version 9.05. Codequality assurance documentation verifies the two operating systems give identical results. TheNITAWL code was used to process cross-section data and KENO-Va was used to model the caskgeometry and predict k,,,^.,. The standard 27-group ENDF/B-IV cross-section library was usedthroughout. All calculations ran 120 generations with 5000 neutrons'tracked per generation inKENO-Va. The first 20 generations were skipped when determining the standard deviation ofthe run. All input files containing geometry specification and material atom densities areincluded in Appendix A.

(3) Identify experimental data and list parameters derived therefrom for use in thevalidation of the model.

The results of the experimental benchmarks modeled with the SCALE 4.2 codes are shown inTable 5. These cases were chosen to represent the materials and geometries used in the caskcalculations such that the code calculational scheme and cross section libraries are benchmarked.Therefore, 239Pu solution and 23SU solution benchmarks are included in the set to represent thefissile solution and the lead wall benchmarks are included to represent the lead walls of thecasks. The benchmark results define the code statistics used in the determination of the K?sm

value for each run. Each benchmark case tracked 5000 neutrons per KENO generation for 120generations with 20 generations skipped. The same scheme was employed in generating cross-sections sets and calculating k ^ ^ as was used to model the worst case geometries. Allparameters required to model these benchmarks are described in the input files given inAppendix B and the references indicated in Table 5.

B6-8



Table 5 Experimental Benchmarks Modeled with SCALE 4.2

Description

PulNO,), Spheres with Spherical Reflectors

24.4 2 Pu/1 sphere with full water reflection

26.3 2 Pu/1 with thin steel shell + full water

34.3 2 Pu/1 with thin steel shell

35.5 2 Pu/1 with 4" concrete shell



Reference

4

5

5

5

6

6

KENO k.^,...

1.01407

1.01064

0.99318

1.02249

1.02516

1.01282

Concrete ReflectedArravs of 93.2 v/t% Enriched Uranv! Nitrate

4x4 Arrav with 67.28 2U/1 Solution

2x2 Anav with 76.09 2U/I Solution

4x4 Arrav with 360.37 2U/1 Solution

4.31 wt% Enriched Optimum Moderated UO

Square arrav with lead wall at 0"

Square arrav with lead wall at 0.26"

Square array with lead wall at 0.77"


Sauare arrav without lead wall

7

7

7

, Pins• g

g

8

8

8

4.31 wt% Enriched Undermoderated UO. Pins

Sauare arrav with lead wall at 0"




Square arrav without lead wall

2 35 wt% Enriched Ovtimum Moderated UO



Square array with lead wail at 1.29"

8

8

8

8

8

. Pint

8

8

8

1.01074

1.00676

1.01108

1.00195

1.00430

1.00043

0.98598

0.98120

1.00225

1.00165

0.99710

0.99544

0.99568

0.99550

0.99414

0.99176

KENO Uncertainty

0.00111

0.00112

0.00127

0.00105

0.00115

0.00101

0.00112

0.00116

0.00132

0.00103

0.00113

0.00111

0.00104

0.00101

0.00105

0.00098

0.00106

0.00111

0.00105

0.00083

0.00096

0.00084

B6-9



Table 5 Experimental Benchmarks Modeled with SCALE 4.2

Description

Square arrav without lead wall

Reference i

I 8 i2.35 wt% F.nriched llndermoderated UO., Pins


Sauare arrav with lead wall at 0.26"


Sauare arrav without lead wall

8 ;

8 i

8

8 • '>

Benchmark Statistics

Bias = 0.00032

KENO k.m_,...

0.98542

0.99022

0.99414

0.99176

0.98365

Standard Deviation = 0.01163

Variance = 0.00014

KENO Uncertainty

0.00086

0.00093

0.00099 .

0.00099

0.00097

(4) State the area(s) of applicability.

The mass limits for fissionable materials applicable to the loading, unloading, storage and on-sitetransportation of specified fissionable material in the Large Bore, the Long Bore, the PRTRGraphite, the One Ton Sample or any cask with a maximum inner volume of 5 L are shownbelow.

275gfor235U,175 g for '"Pu, 233U,237 Np, 2<IAm, 2«Am, w Cm, and 2«Cm,

The Sum of Fractions method defined in Table 6.1 in PNL-MA-25 may be used to determinecompliance for mixtures of fissionable material. Fissionable material more reactive than 239Pu,i.e., 2"™Am, 243Cm, 2<5Cm, 2wCf, or 251Cf have not been analyzed and thus are not allowed underthese limits; however these materials are considered to be insignificant for the purposes ofcriticality safety provided the mass does not exceed the safeguards accountability limits. PacificNorthwest National Laboratory currently has none of these restricted materials in accountablequantities. These materials can only be obtained in accountable quantities as a source and thuscould not be accidentally obtained. Therefore, violation of this restriction is not credible.

The 12" edge-to-edge spacing requirement is in effect between the cask and other fissionablematerial. Spacing requirements between the cask and other heavy metal reflectors are notnecessary because the cask was proven to be subcritical with an infinite lead reflector.

B6-10



(5) State the bias and the prescribed margin of subcriticaliry over the area(s) ofapplicability. State the basis for the margin.

Calculational results indicate that the overall code bias based on benchmark calculations given inTable 5 calculated using KENO-Va tracking 5000 neutrons per generation is 0.3 ink. The meanof all benchmarks is 0.9997 and the standard deviation of the mean is 12 mk. If these values areapplied to the modeled scenarios using the methodology given in Reference 3, the reactivity willnot exceed 0.988 including experimental error and biases. The margin of subcriticality istherefore at least 12 mk and assumes optimum conditions and a loss of contingency error. Themargin of subcriticality was calculated with a 95%/95% confidence.

Discussion of Loss of Contingencies

The Large Bore, Long Bore, PRTR Graphite and One Ton Sample Cask scenarios were modeled with.tolerances on each of the geometric parameters of the casks. The direction of the tolerance was chosento create a more reactive situation such as allowing a larger mass in the cask or allowing a more reactiveconcentration of material. In addition, the maximum cask volume limit is set based on a sphericalgeometry; most casks at the Laboratory have a cylindrical bore and thus will be less reactive. Therefore,the most reactive geometric models were considered.

A loss of mass contingency error would be caused by exceeding the mass limit in the cask. This .scenario was examined by modeling the minimum water reflected critical mass (820 g 23SU and 530 g23'Pu) in each of the casks. In all cases, the margin of subcriticality was greater than 100 mk. Thisaccident scenario was also modeled in the 5 L lead cask. The result was a subcritical margin of 12 ink.Therefore, an accident where the mass limit is exceeded will not result in criticality.

An increase in the volume of the cask is not a credible accident for the Large Bore, the Long Bore, thePRTR Graphite and the One Ton Sample Casks as their geometry is known and documented andtolerances were added to the nominal dimensions when modeled. However, the use of the 5 L volumelimit on a larger cask which does not meet this requirement is possible. Therefore, the spherical caskwas modeled with the fissile material at the mass limit and at optimum concentration in an increasedvolume. These cases were subcritical with a margin of at least 100 mk.

An increase in the thickness of the lead shielding or stacking lead bricks around the cask will also notresult in criticality. To ensure this, the 5 L cask and the Large Bore Cask were modeled at the mass limitwith .an critically infinite lead thickness of 28". The subcritical margin was greater than 100 mk in all

The purpose of this memo was to provide the technical bases for the subcriticality of storage andhandling of fissionable material scrap of various compositions in small bore transfer casks and lead pigswith lead shielding. The analyses assumed optimum water moderation of the fissionable material

B6-11


NCS Basis Memo 96-2December 30,1996

•Page 11

located inside the casks and demonstrated subcriticality during normal operations and following the lossof a single contingency including over batching, an increase in the reflector thickness (i.e. stacking leadbricks around the cask) and an increase in the cask volume (using the mass limit for a larger cask).These analyses bound all possible loss of contingency scenarios and ensure the double contingencyprinciple is met. In conclusion, batch limits for the amount of scrap in the Large Bore, the Long Bore,the PRTR Graphite and the One Ton Sample Casks have been determined. The limit for 23SU as the onlyfissionable material is 275 g 23iU. The limit for other types of fissionable material except 2<2mAm, ™Cm,245Cm, 249Cf, and 2slCf is 175 g of fissionable material. These limits are also valid for lead shieldedcasks with a maximum inner volume of 5 liters and an unlimited lead thickness. The 12" edge-to-edgespacing requirement is in effect between the cask and other fissionable material but spacing requirementsbetween the cask and other heavy metal reflectors are not necessary.

Concurrence:Senior SpecialistCriticality Safety Analysis

B6-12


•:S i i s is HBO 85-2:e=e=Mr 30. IS5S:ece 12

-??sndix A Input Files for Worst Use Scenarios

input f i l e for Optinrjm Pu Concentration Determination as given inTable 1-nitswl:ss 82 2 3 4 !3

19 9 15 20 .!SS 500 6 0 0 0

0 0 4 0 00 0

it! S4239 -23527•23S42 E2000 1001

3 " 23527 293 30.0 6.801SE-05 1

1 15.9951 l.S17SE»0323532 253 3

0.0 3.0514E-05 1' 1 15.9954 1.S335E-03

23937 253 30.0 9.32CSE-05 11 15.SSS4 1.32S9E*03

23942 253 30.0 1.05E1E-04 1

1 15.9554 1.16/SE-03A" f293

-23932 -235378016

15.5525 0.00001.0079 2.0024E-04

1 115.0836 0.00501.0079 1.6351E-G4

1 114.3710 0.00001.0079 l.<60SE*M

1 113.7765 • O.OOOO

1.0079 1.2S63E-041 1.000

end-kenova

• 460 g Pu Sphere at 27.0 g/1 6.3" Radius 8" Lead Refl * FV3read paremMe-700 gen-120 nsk-20 l i b -4 npg-5000fix-yes fdn-yes tba-60.0 nfb-8000end param

' • MIXTURES *

read mixt sct -1i.ix-1'Pu at 27.0 g/1

23527 6.6016E-C58016 3.3383E-021001 6.6/65E-02

mix-2•Lead

82000 3.3133E-02oix-3•Water

8016 3.3426E-021001 6.6656E-02

end mixt

' * GEOMETRY *

read geomrait 1COT,--PU Sphere with Lead Shielding and Fk'X"sphere 1 1 15.56sphere 2 1 36.23cubsid 3 1 6?55.23end cecffl•er.j ii-.ssr.d

453 g ?y Sphere at 32.0 c/1 5.raa; par=3t-5-703 cer.-123 nsk-20flx-i 'es fd-.-\eser.S paraa

'* ":>TJS=S *

" SiC:iL;s S" Lead F.efl

iib-4 npc-50C-0tpa-SO.O r,fD-&0S0

mix-2'Lead

mix-3'Water

2353280161001

82000

80161001

end mixt

' * GEOMETRY

8.0514E-053.3374E-026.6/48E-C2

3.3133E-02

3.3428E-026.6856E-02

*

read geonunit 1ccxr.-"Pu Sphere with Lead Shielding end F R"sphere 1 1 . 15. OSsphere 2 1 35.40cuboid 3 1 6p65.40end gecwend dataend-kenova460 9 Pu Sphere at 37.0 g/1 "5.7- Radiusreed parara

i" Lead Refl • FIR

tne-700 gen-120fix-yes fdn-yesend peram

nsk-20 l ib-4tba-60.0

npg-5000nfb-6000

' * KIXTURES •

read mixt ECt-1

•pu a t 37.0 g/123937

80161001

mix-2"Lead

82000mix-3'Water

80161001

eni mixt

' * GEOMETRY

9.3209E-053.3365E-026.6731E-02

3.3133E-02

3.3426E-026.6856E-02

unit 1conKPu Sphere with Lead Shielding snd FWR"sphere 1 1 14.37sphere 2 1 34.69'cuboid 3 1 6p54.69end.oecciend dataend-kenova450 g Pu Sphere at 42.0 gn 5.4" Rsdius S" LeEd Refl + FWRreed pErEmtrr,£-7C0 oen-120 nsk-20 "lib-4 npg-5000fix-yes fdn-i'es tbc-50.0 nfb-6000

•* MiXTL'RES *

reed mix! sct-1

"Pu at ^2.0 c/12"^2 1.05S1E-K

B6-13


NCS Basis Ksum 96-2Cecwfcer 30. 1996Page 13

82000 3.3133E-02

80161001

er.d mixt

•* GECK-TRV

read geomunit 1

3.342SE-026.6S56E-02

•

coa-"Pu Sphere with Lead Shielding and FWR"spherespherecuboidend geonend dataend

1 12 13 1

13.7834.10

6p64.10

Input f i l e for Optimum MSU Concentration Determination as given inTable 1-nitewlOSS 82 2

19 91SS 500 8

0 00 0

2SS 92235-23545 82000

3 " 23545 2530.0 1.1530E-04

1 15.999423555 293

. - n N 0.0 1.4092E-04•':•'•) 1 15.9994'•--is 23550 293

0.0 1.2811E-041 15.9594

23560 2930.0 1.5373E-04

1 15.95544-* f293

end-fcenova

3• 15

04

-235501001

31

1.07ME*0331

8.7610E*0231

9.6396E-KI231

8.0288E-KI2

t20

00

-23555

18

00

-235508016

15.76101.0079

114.7412

1.00791

15.21711.0079

114.3198

1.00791

0.00001.180!E»04

1.0000.0000

9.6503E-031.000

0.00001.0616M4

10.0000

8.8436E-031.000

738 g U235 Sphere at 45.0 g/1 6.2" Radius 8" Lead Refl + FiiRread param •tme-700 .cen-120 nsfc-20 I1b=4fix-yes fdn-yesend param

'* MIXTURES •

read mixt sc t -1mix-l•U235 at 45.0 g/1

23545 1.1530E-048016 3.3348E-021001 6.6597E-02

mix-2•Lead

82000 3.3133E-02

tba-60.0npg-5000nf»-8000

sphere 2 1cuboid 3 1end oecmen<3 da t aend•kenova733 g U235 Sphere et 50.0 g/1rs;d p=re:atr:e-700 gsn-120 nsk.-;•flx-^es fan-yesend parem

6.0" Radius 6" Lead Refl •

l i b - 4 npg-5000tba-50.0 nfS-SOOO

'* MIXTURES •

read mixtmix-l

sct-1

'U235 at 50.0 g/12355080161001

mix-2•Lead

82000

'Water50151001

end mixt

1.2811E-043.3340E-026.6679E-02

3.3133E-02

3.3428E-026.6655E-02

' • GECKETSY •

read seemunit Icar.-"U235 Sphere with Lead Shielding and FWR"sphere 1 1 15.22sphere 2 1 35.54cuboid 3 1 6P65.54end geonend dataend-kenova738 g LJ23S Sphere at 55.0 g/1 5.8" Radius 8" Lead Reflread par;

nsk-20tra-700 gen-120fix-yes fdn-yesend paran

lib-4 npg-5000tba-60.0 nfb-8000

* KIXTURES '

read mixt sct-1oix-1•U235 at 55.0 g/1

23555 1.4092E-048015 3.3331E-02iOOl 6.6662E-02

mix-2•Lead • '

82000 3.3133E-02mix-3'Water.

8515 3.3428E-021001 6.6S56E-02

end mixt

ixt

' • GECMET5Y •

read c=Da

CD:--L'235 Spf.i-3 t : th Lea: Shis

read c e ^unit 1CO3--U235 Spheresphere 1 1sphere 2 1catoid 3 1

i t h Lead Shielding and fiffi-14.7435.05

6=55.06

B6-14


KCS Basis nemo 95-2tece&er 30. 19S5Page 14

-kenova738 g U235 Sphere at 50.0 g/1read paramtrae-700 gen-120 nsk-2<fix-yes fdn-yesend param

•• KIKTURES *

5.6" Reiius S" Lesd Ref) + fKR

l ib-4tb£-60.0

npg-5000nfb-8000

read mixt sct-1mix-1'U235 at 60.0 g/1

23560 1.5373E-048016 3.3322E-021001 6.6544E-02

mix-2"Lead

62000 3.3133E-02

mix-3

'Water

8016 3.342SE-021001 6.6856E-02

end mix t

• • GECHETRY .*

read gsomunit 1c<»i--U23S Sphere ui th Lead Shielding and FVR-sphere 1 1 14.32sphere 2 1 34.64cuboid 3 1 6pS4.64end oeomend dataend

Input Fi le for asU Scrap in the Large Bore Cask as given in Table 3-nitawlOSS 82 2 3 4

19 9 IS 20IS! 500 7 0 0

0 0 3 00 0

18

2SS

3 "

4**

S2235• 8200035122

-351221001293

-35558016

21

f2S3

0.0 3.1335E-C41 15.9994 3.9259E-02

3555 293 20.0 1.4097E-04 1

1 • 15.9994 8.7578E»023560 2S3 2

0.0 1.5373E-C4 11 15.9994 8.0288E*C2

-3560

5.5799 0.00001.0079 4.3244E-KI3

• 1 1.0005.5799 0.00001.0079 9.646SE-KI3

1 15.5799 0.00001.0079 8.S438E-03

1 1

end•kenova820 9 U235 Cylinder a 122.3 9/1 in large Bore Increase Dread psremtee-700 sen-!20 nsk-20 l i b -1 npg-5000 nfb-SOOOfix-yes fc"n-y=s pit-yes r-jr.-yes tba-50.0

d

KIXTD5ES

sct-1read mixt•fuelMx-1

35122 3.1325E-04£0!5 3.32!2i-C21001 5.54^1-02

82000 3.3130E-02•tetermix-3

8016 3.3426E-02

1001 6.6S55E-02

end mixt

'• G-CBETSY

read sew

unit 1

CQ--"U235

cylinder

cylinder

Cylinder

1 1 •3 1orig2 1

Large Bore Cask"5.5799 68.5800 0.0000

5.5800 68.5800 0.0000

0.0000 0.0001

cylinder 2 1 26.7650 95.4800 -26.9000

orig 0.0000 0.0001

cylinder 3 1 56.7650 125.4S00 -55.9000

orig 0.0000 0.0001

end gecffl

end data

end

-kenova

359 g 0235 Cylinder a 55.0 g/j in Large Bore Increase 0read paranitme-700 sen-120 nsk-20 11b-4 npg-5000 rfix-yes fdr.-yes pit-yes run-yes tba-60.0end param

•* HIXTURES

read mixt sct-1'Fuelinix-l

3555 1.4097E-04

8015 3.3331E-02 .

1001 6.6562E-02

"Lead

mix-2

82000 3.3130E-02•Watermix-3

8016 3.342SE-021001 6.6856E-O2

end mixt

•• GEOMETRY

read gecoiunit 1coo-"0235 Cylinder Large Bore Cask"

1 13 1orig2 1crig3 1orig

5.57S95.58000.000026.76500.000055.76500.0000

68.580068.58000.000195.48000.0001

125.48000.0001

0.00000.0000

-25.9000

-56.9000

cylindercyl inder

cylinder

cylinder

end gecfflend dataend

Input File for "EU Scrap in the Long Bore Cask as given in-nitawlCSS

1SS

821950000

9223582000'35! 380.0 3j

29700

•3513S

hi'.543/E-e^

31503

•3552S0162I

A2000

•3=55

4.3:991.CC79

I

IS

00

0.03003.E205E-C3

l.KO

B6-15


KCS Essis Hedo 96-2Oxe.rser 30. 1SSSPiSS 15

3562 253 20.0 1.5952E-04 1

• 1 15.9994 7.7314E*023555 293 2

0.0 1.40S2E-04 11 15.5554 8.76!0E*02

f253

4.3099 0.00001.0079 8.5I62E-MJ3

1 14.3D99 0.00001.0079 9.6503E*03

1 1.000

-kenova

820 9 U235 Cylinder a 138.3 g/1 in Long Bore Increase 0

read par'amtrae-"700 gen-120fix-yes fcin-yesend param

nsk-20pH-yes

npg-5000 nfb«3000tbo-60.0

•* MIXTURES

read mixt•Fuelcix-1

sct-1

35138 3.5437E-0460161001

•Leadr.ix-2

S2000'Watermix-3

80161001

end mixt

' * GEOKETRY

.,„,„„„-•.';:-;ec«iCOI--0235cylindercylinder

cylinder

cylinder

end geanend dataend-fcenova369 9 U235read paremt/ae-700fix-yesend param

'* MIXTURES

read mixt'FuelBiix-1

3.3183E-026.6367E-02

3.3130E-02

3.3428E-026.6555E-02

Cyl inter1 13 1-orig2 1orig3 1ori9

Cylinder a

gen-120fdn-yes

set" !

3562 1.5S62E-046016

• IOOI'Lea;

S2300

60161001

3.3315E-026.6535E-02

3.3i::E-02

3.3425E-026.65S6--02

Long Bore4.30594.31000.000024.86000.000054.86000.0000

Cask"101.6000 0.0000101.6000 0.00000.0001

129.2938 -27.65380.0001

159.2938 -57.65380.0001

62.3 o/l in Long 8ore Increase D

nsk-20pit-yes

l ib-4 npg-5000 nfa-8000run-yes tba-60.0

unit 1CCQ--U235 Cylinder Long Bore Cask-cylinder 1 1 4.3099 101.5000 0.0000cylinder 3 1 4.3100 101.6000 0.0000

orig 0.0000 0.0001cylinder 2 1 24.8600 129.2933 -27.6533

crig 0.0000 0.0001cylinder 3 1 54.6600 159.2938 -57.6933

orig 0.0000 0.0001end cecfflend dataend-kenova325 g U235 Cylinder a 55.0 5/1 in Long Sore Increase Dreed paramtire-700 oen-120 nsk-20 l ib-4 npg-5000 nfb-8000fix-yes fdn-yes pit-yes run-yes tba-50.0end paraa

' * HKTIRES

read mixt sct-1'Fuelnix-1 ' ' ' '

3555 1.4092E-0480!6 3.3331E-022001 6.6552E-02

'Lead. mix-2

82000 3.3130E-02'Watermix-3

8016 3.3428E-021001 6.6856E-02

end mixt

' * GEOMETRY '

Input F i le for a iU Scrap in the PRTR Graphite Cask as given in 'Tabl

8219

50000

315

03

92235 -3518582000 100135155 293

0.0 4.7297E-041 15.95=4

3553 2930.0 2.1291E-04

1 15.9594 5.7358E-023555 - 293 20.0 1.40S2E-M i

1 15.9594 8.7610E-52

35638016

21

" 21

200 00 0

-3555

4.6274 0.0000J.K-75 2.8555E»03

• 1.0004.62:4 0.00001.0079 6.3776E>03

1 14.6274 0.00001.0079 S.6503E-S3

1 1.000

B6-16


NCS Sasis Hero S6-2Decesber 30. 1SS5Page 16

-kenova620 9 U235read pararoras-700f lx-yssend param* * * * * * * * * * *

' * MIXTURES

read mixt'Fuel

mix-13518580161001

•Leadmix-2

82000•Watermix-3

80161001

end mixt* * * * * * * * * * *

•' GEOKETRY* * * * * * * * * * *

read ceomunit 1CM--U23Scylindercylinder

cylinder

cylinder

end geonend dataend-kenova369 g- U235read paraaitse-700fix-yesend param

•« MIXTURES* * * * * * * * * * *

read raixt•Fue l 'mix-1

Cylinder a

gen-120fdn-yes

sct-1 .

4.7297E-043.3102E-026.6203E-02

3.313CE-02

3.3426E-C26.68S6S-02

Cylindsr1 13 1orig2 1orig3 1orig

Cylinder a

gen-120fdn-yes

sct-1

3583 2.1291E-0480151001

'Leadmix-2

82000'Watermix-3

80161001

end mixt

' • GECKETSY

read cso.iiunit 1COB-TB35cylindsrcylinder

cylinder

cylinder

3.3281E-026.5562E-02

3.3130E-02

3.3426E-026.65S5E-02

Cylindsr1 13 1orio2 1eric3 i

184.6 9/1 i

nsk-20pit-yes

PRTR Graphi4.62744.62750.000019.78000.0000 .49.78000.0000

PRTR Greph Increase O

l ib -4run-yes

Cask"66.040066.04000.000184.05000.0001

114.05000.0001

83.1 9/1 in PRTRGrapt

nsk-20pit-yes

PS7R Graphi4.62744.62750.000019.7=00O.COC'O49.7300

l ib -4run-yes

Cask-66.040066.04000.C00!64.05030.00C1

114 c - ' ' 1

0.GCC1

npg-5000 nfb-8000tba-50.0

O.00000.0000

-18.0100

-48.0100

1 Increase 0

npg-5000 nfb-8000tba-50.0

0.00000.0000

-13.0100

.£= r.;-.n

end ceanend dataend-kencva244 g U235read pareatme-700fix-yes

' * KiXTUSES

read mixt•Fuelmix-1

3555801610C1

"Leadmix-2

82000"Watermix-3

80161001

end mixt• • • * * * * * * * *

' '* GEOKETRY***********read geonuni t 1com-'u"235cylindercylinder .

cylinder

cylinder

end gecnend dataend

Cylinder 3

gen-120fdn-yes

sct-1

1.4092E-043.3331E-026.6552E-C2

3.3130E-02

3.342SE-026.6856E-02

Cylinder1 13 1orig2 1orig3 1orig

55.0 g/1 in

nsk-20pit-yes

PRTR Graph)4.62744.62750.000019.78000.000049.78000.0000

PRTR Graph Increase D

l ib -4run-yes

Cask"66.039966.04000.000184.05000.0001

114.05000.0001

npg-5000tba-50.0

0.000O0.0000

-18.0100

-48.0100

Input File for "sLf Scrap in the One Ton Sample Cask as giTable 3-nitawlOSS

lss

t2SS

3 "

4 * *

er.d-kenova820 g U235read parantrce-700fix-yesend pars.n'*******'**

8219

50000

922358200035392

29700

-353921001293

0.0 1.0036E-031

35176' 15.9994

2930.0 4.5170E-041

355515.9994

2930.0 1.4092E-C41 ' "

f2S3

Cylinder a

Sen-120fdn-yes

351.7 g/1 ir

nsk-20pit-yes

31503

-351768016

21

1.2082E»0221

2.7156E»0221

8.7610E+02

1 One Ton

l ib-4run-yes

42000

-3555

4.30991.0079

14.30991.0079

14.30991.0079

1

Increase I

npg-5000tba-50.0

nfo-SOOO

ven i n

IS

00

0.00001.3308E»03

1.0000.0000

2.9912E*031

0.00009.6503E-03

1.000

)

nfb-3000

B6-17


NCS Basis K«ro S5-2Oec«0er 30. 1SS5Fsge 17

read mi xt•Fuel

sct-1

IF ' '35392 1.0036E-0380161001

'Leadir.ix-2

82000Vateruiix-3

60151001

end mixt***********• • GEOMETRY' * * » * » * . » * *

read geonunit 1con-"U235cylindercylinder

cylinder

cylinder

end geaaend dataend-kencva369 g U235read paramtme-700n-.-yes' ' • • • ' • ' • • ' r a m

•• KIXTURES

read mixt•Fuelnix-1 '

3.2735E-026.S471E-02

3.3I30E-02

3.342SE-026.6S55E-02


Cylinder a

gen-120fdn-yes

sct-1

35175 4.5I70E-0480161001 •

•Leadmix-2

82000"Wateroix-3

60161001

end mixt

' • GE01ETRY

read geanunit 1cos-"U235cylinder

cy.inder

cylinder

cylinder

en* qeciMta

•kenova115 o U235r=ai param •--r.e-703fix-yes

3.3115E-026.6233E-02

3.3130E-02

3.3428E-026.6855E-02

Cylinder1 1

orig2 1orig3 1oric

Cylinder a

ge-.-!20fc-.-yes

One Ton4.30994.31000.0000

22.3200 •0.0000

52.32000.0000

176.3 g/1

nsk-20pit-yes

One Ton4.3099

4.31000.0000

22.32000.0000

52.32000.0000

55.0 g/1 1

r.sk-20pit-yes

Cask"35.877535.87750.000157.22130.0001

87.22130.0001

in One Ton

l ib-4run-yes

Cask"35.S775

35.87750.000!57.22130.0001

87.2213o.ecoi

n One Ton

l ib-4r^r.-yes

0.00000.0000

-21.3438

-51.3433

Increase D

npg-5000 rtba-50.0

0.0000

0.0000

-21.3433

.si 3435

Increase D

nr=-5000 rt:a-:C-.C-

ifb-8000

A - 5 K 0

' • KIXTUKS

read mixt•Fuelrsix-1

355580161001

•Leadmix-2

82000"Waternix-3

80161001

end fflixt

• • GEOMETRY* * * * * * * * * * *

read ceomunit 1cor.-"U235cylindercylinder

cylinder

cylinder

end geanend dataend

sct-1

i.4052E-043.3331E-025.6562E-02

3.3130E-02

3.3428E-026.6856E-02

Cylinder1 13 1orig2 1'orig3 1orig

One Ton4.30994.3100- -0.0000

22.32000.0000

52.32000.0000

Cask"35.877135.87750.000157.22130.0001 •

87.22130.0001

Input Fi le for B!Pu Scrap in the Large Bore C-nitawlOSS

lss

t2SS

3 "

4**tend-kenova530 g Puread paramt-ne-700

end param***********•• RIXTl'SES***********read ir.ixt•FuelBliX-.l

397980151001

' leadrr.ix-2

E20D0

8219

50000

942398200039790.01

3934

29700

-39791001293

1.9904E-O415.9994

2930.0 8.6408E-051

393215.9994

2930.0 8.0614E-051

f293

Cylinder a

oen-120

sct-1

1 CC04E-04

3.3295E-025.6585E-02

3.3130E-02

1-5.9994

31503

-39348016

21

6.1959E-0221

1.4305E*0321

1.6336E»03

79.0 g/1 in Large Sore

nsk-20 l ib -4

0.00000.0000

-21.3438

-51.3438

*sk as given in Table 3

42000

-3932

5.57991.0079

15.57991.0079

15.57991.0079

1

Increase D

npg-5000

18

00

0.00006.6249E»03

10.0000

1.5757E*041

0.00001.6891E*04

1

nfo-8000

B6-18


HCS Basis Herc) 96-2Oecerier 30.Page 18

ir.ix-38016

1001

end m ix t

• * GEOMETRY

read geom

unit 1COT-"Pu

cylindercylinder

cylinder

cylinder

end geomend dataend-kenova230 9 Puread paramtme-700 'f ix-yesend param

'« MIXTURES


19S5

3.3428E-02

6.6856E-02

Cyl inder

1 1

3 1orig2 1crig3 1orig

Cylinder a

gen-120fdn-yes

sct-1

3934 8.6408E-0580161001

•Leadmix-2 .

82000•k'ater .mix-3

80151001

end mixt

'* GEOMETRY

read geomunit 1COTi-"Pu

cylindercylinder

cylinder

cylinder

end geomend dataend-kenova215 g Puread paraa3=6-700fix-yesend pararr.

'* MIXTURES

read mixt

ir.ix-1

3.3370E-026.6740E-02

3.3130E-02

3.3428E-026.6856E-02


Cylinder a

gen-120fdn-yes

sct-1

3932 8.C6!i;-053.3374E-C2

Large Bore5.57995.58000.000026.76500.0000

55.76500.0000

Cask"63.580068.58000.000195.48000.0001

125.48000.0001

0.00000.0000

-26.9000

-55.9000

34.3 g/1 in Large Bore Increase D

nsk-20 .pit-yes

Large Bore5.57995.58000.000026.76500.0000

55.76500.0000

lib-4run-yes

Cask"68.580068.58000.000195.48000.0001

125.48000.0001

npg-5000 nfb-8000tba-60.0

0.00000.0000

-26.9000

-56.5000

32.0 g/1 in Large Bcre Increase D

nsk-20pit-yes

lib-4rjn-yes

r.pg-50C0 nfb-3003»3-50.0

mix-282000

"Water •nix-3

80151001

end fiixt

• • GEOMETRY

read geom

unit 1ccvn-"pucylindercylinder

cylinder

cylinder

end gecxnend dataend

3.3130E-02

3.3428E-026.6656E-02

Cylinder1 13 1orig2 1crig3 1"orig'

Large Bore5.57995.53000.000025.7550-0.0000

56.76500.0000

Cask"68.530068.58000.0001S5.4500C.0C01

125.48000.0001

0.00000.0000

-25.SCC0

-56.9000

Input File for aJPu Scrap in the'Eong Bore Cask as given in Table 3-nitawlOSS

1SS

t2SS

3**

8219

50000

94239820003989

29700

-39891001293

0.0 2.2521E-041

393915.9994

2930.0 9.7744E-051

393215.9994

2930.0 8.0614E-051 15.9994

31503

-39398016

21

5.4730E*0221

1.2643E*0321

1.5335E»03

42000

-3932

4.30991.0079

14.30991.0079

I4.30991.0079

1

18

00

0.00006.0285E-0'

1"0.0000

1.3926E»041

0.00001.6S91E-04

14 " f293tend-kenova530 g Pu Cylinder a 89.4 g/1 in Long Bore Increase Dread paremtiae-700 gen-120 nsk-20 l i b -4 npg-5000 nfix-yes fdn-yes pi t -yes run-yes tba-60.0end paran

' * MIXTURES

read mixt sct-1•Fuel • •

mix-13969 2.2521E-04

8016 3.3277E-021001 6.6554E-02

•Leadmix-2

S20C0 3.3130E-02•Hatern'.x-3

8016 3.3428E-C21001 5.6S56E-02

end nixt

• • GEOMETRY

read geos

C D T - " ? - 1 Cy l inder tcng Sore Cask"

B6-19


HCS Bssis f*™ 96-2Decetter 30. 19SSPage 19

cylindercylinder

1 13 1orig2 1orig3 1orig

gen-120fdn-yes

cylinder

end gecrnend dataend-kencva230 g Puread paramtus-700 'fix-yesend pararc

'• MIXTURES

read rr.ixt sct-1•ru-1

mix-13939 9.7744E-058016 3.3363E-021001 6.672SE-02

•Leadnix-2

82000 3.3130E-02'Watermix-3

8016 3.3428E-021001 6.6856E-02

end fflixt

4.30994.31000.000024.65000.000054.850.0000

101.6000101.60000.0001

129.29330.0001

159.29330.0001

0.00300.0000

-27.6S33

-57.6933

Cylinder a 38.8 g/1 in Long'Bore Increase D

nsk-20pit-yes

l ib-4 r.pg-5000 nfb-30run-yes tba-50.0

0.00000.0000

ft-.-, seemunit 1•COH--PUcylindercylinder

cylinder

cylinder

end gecoiend dataend-kencva190 g Pu Cylinder a 32.0 g/1 in Long Bore Increase Dread paramtme-700 gen-120 nsk-20 l i b -4 npg-5000 nfb-8000fix-yes fdn-yes pit-yes run-yes tba-50.0end peraa

Cylinder1 13 1orig2 1orig

'3 1orig

Lcig Bore4.30994.31000.000024.86000.000054.860.0000

Cask"101.6000101.60000.0001

129.29380.0001

159.29380.0001

read j•Fuelsix-1

•Leadiix-2

i

?!

r.ixt sct-1

3932 8.0514E-C580151001

•2000

80161001

ix t •

3.3374E-025.674SE-02

3.3I30E-C2

3.342SE-026.6355E-02

read oecmun i f lcon-'Pucylindercylinder

cylinder

cylinder

end seemend dataend •

Cylinder1 13 1orig2 1orig3 1crig

Input F i l e f o r " 'Pu ScrTable 3- n i t awlCSS

1SS

t2SS

3. .

4«*

tend-kenova530 g Puread paramtoe-700f ix-yesend parani

'* KIXTOR-S

read mixt•Fuel

82• 1 9

50000

94239820003S119

Long Bore4.30994.31000.000024.85000.000054.550.0000

Cask"101.6000101.60000.0001

129.29330.0001

159.29380.000!

0.00000.0000

-27.6933

-57.6938

•ap in the PRTR Graphite Cask as g

29700

• -39119W01293

0.0 3.0079E-041

395215.9994

2S30.0 1.304SE-041

393215.9994

•2930.08.0614E-051

f293

Cylinder a

sen-120fdn-yes

sct-1

39119 3.0079E-0480161001

'Leadir.ix-2

82000'Watermix-3

80161001

end mixt

' • GEOMETRY

read gecQunit 1cors-'pycylindercylinder

cylinder

cylinder

3.3227E-026.6453E-02

3.3130E-02

3.3428E-026.6856E-02

Cylinder1 13 1orig2 1c-rig3 1crig

15.9994

119.4 g/1 i

nsk-20pit-yes

PST5 GrssM4.52744.62750.000019.78000.000049.73000.0000

31503

-39528016

21

4.0916E»0221

9.4636E*0221

1.5335E*03

PBTR Graph

l ib -4run-yes

CsSk"66.040065.04000.000164.05000.0001

114.C5000.0001

42000

-3932

4.62741.0079

14.62741.0079

14.62741.0079

1

Increase 0

npg-5000tba-60.0

O.COOO0.0000

-18.0100

-43.0100

1ven in

18

00

0.00004.5069E*03

10.0000

1.0424E»M1

0.00001.6S91E-04

1

nfb-8000

B6-2O


NCS Eisis Memo SS-2December 30. I9S6Page 20

end-kenova230 9 Pu Cyl inder a 51.8 g/1 i n PRTR Graph Increase 0read parsm

0.0000 0.0001

Ke-700fix-yesend param

• • KIXTUSES


gsn-120fan-yes

sct-1

3952 1.3049E-0480161001

•Leadmix-2

82000•'Watermix-3

80161001

end mixt .

• • GEOMETRY

read geomunit ICOTr'Pucylindercylinder

cylinder

cylinder

end S2OTi

end dataend-kenova142 g Puread paramtoe-700fix-yesend param

•* KIXTURES


3.3341E-026.6661E-02

3.3130E-02

3.3426E-026.6656E-02


Cylinder a

gen-120fdn-yes

sct-1

3932 8.0614E-0580161001

'Lead»ix-2

82C0O'Watermix-3

6016• 1001

end n;ixt

' * C-ECKETRY

3.3374E-026.674SE-02

3.3130E-02

3.3428E-026.6856E-02

nsk-20ptt-yes

PRTR Graph4.62744.62750.000019.78000.000049.78000.0000

l ib-4run-yes

i Cask"66.040066.04000.000184.05000.0001

114.05000.0001

32.0 g/1 in PRTR Graph

nsk-20pit-yes

l ib -4run-yes

npg-5000 nfb-8000tba-60.0

0.00000.0000

-18.0100

-48.0100

Increase D

npg-5000 nfb-8000tba-60.0

r=;d CSDTIur.it 1csr.-"Py Cylinder- PRTR Grsphi Cask"cyl i nder 1 1 4.5274 65.04C0 0.0000Cylinder 3 1 4.6275 66.WOO 0.0G00

orig 0.0009 0.0001cylinder 2 1 1S.7S00 64.0530 -13.0100

Orig 0.0000 0.0001

end gecraend dataend

Input Fi le for v'Pu Scrap in the One Ton Sanple Cask as given inTable 3-nitawlCSS

1SS

t2SS

3«*

tend-kenova530 9 Puread para™tme-700fix-yesend parent

' * KIXTURES

read mixt'Fuelmix-1

8219

50000

9423982000352=3

C-.C1

39110

29700

-392531001

6.37S5M415.5594

2930.0 2.7711E-C41

393215.9994

2530.0. 8.0614E-051

f293

Cyl inder a

gen-120fdn-yes

sct-1

39253 6.3785E-0480161001

'Leadmix-2

82000'Watermix-3

80161001

end fflixt .

' * GEOMETRY

read georaunit 1can-"Pucylindercylinder

cylinder

cylinder

end seenend dataend-kenova230 g Pu •read paraat=e-7C0fix-yes

3.3001E-026.6001E-02

3.3130E-02

3.3428E-026.6856E-02

Cylinder -1 13 1orig2 1orig3 1crig

Cylinder a

cen-120fen-yes

15.5594"

253.2 g/1 i

nsk-20pit-yes

One Ton4.30954.31000.0000

22.32000.0000

31503

-351108016

i.1

1.5163E-0221

4.4434E*0221

1.5335E*03

One Ton

l ib -4run-yes

Cask"35.877535.87750.000157.22130.0001

42000

-3532

4.30^51.0075

14.30991.0079

14.30991.0079

' l

Increase 0

nps-5000tba-60.0

0.00000.0000

-21.3438

52.320 67.2213 -51.34380.0000

110.0 9/1 i

nsk-20pit-yes

0.0001

One Ten

l ib-4r-jn-yes

Increase 0

rpg-5000tba-50.0

18

C0

0.00002.UC»*!3

10.0000

4.8944E*03I

0.00001.6891E-04

1

nfb-8000

nfo-SOOO

B6-21

NCS BssiS K*w S6-2Dace^er 30. 1595


' 39110 2.77UE-048016 3.3242E-021001 6.64S5E-C2

'Leadr.lx-2

82000 3.3130E-C2"Wateraix-3

8016 3.3428E-021001 6.6SS6E-02

end mixt***********•• GEOKETW

read' geomunit 1ccffi-"Pucylindercylinder

cylinder

cylinder

end ceanend d3taend-kenova67 g Pu

Cylinder One Ton4.30994.3100O.OOOO-

22.32000.0000

52.320• 0.0000

y1 13 1orig2 1orig3 1orig

Cask"35.8775 0.000035.8775 0.00000.000157.2213 -21.34380.0001

87.2213 -51.34330.0001

7 g u Cylinder a 32.0 g/1 in One'Ton Increase Dread paramt—-7.00 gen-120 nsk-20 l i c -4 npg-5000 nfb-8000*• X ) s fdn-yes pit-yes run-yes tba-SO.O


sct-1

3932 8.0514E-058016!0W

•leadir.ix-2

82000•Waterir.ix-3

80161001

end mixt

' • GE0HETRV

reed geconunit 1ccffi-"Pucylindercylinder

cylinder

cylinder

3.3374E-026.6748E-02

3.3130E-02

3.342SE-026.6S56E-02

Cylinder1 13 1orig2 !ori a3 1crio

One Ten4.30994.31000.0000

22.32000.0000

52.3200.0000

Cask"35.877535.87750.000!57.22130.000!

87.22130.CCG1

0.00000.0000

- 2 ! ,343

-SI.3435

19500

00

94239620003934

9500

-39341001293

0.0 8.6408E-051 15.95=4 1

1501

801621

.4305E*03

2000

5.57591.0079

1

00

0.00001.5757E-04

14 " f293tend-kenova230 g Pu Cylinder a 34.3 g/1 in Large Bore Increase Lead Thickness to12.4-ii pe.-a-

Input Fi le for :; iPu in tile Larce Bor-e Cask with Increased Le3dReflection as given after Table 3

fr:e-70?f ix -yesend param

' * MIXTURES

read mixt'Fuelmix-1

sen-120 nsk-20fdn-yes pit-yes

sct-1

3934 8.6408E-0580161001

'Leadmix-2

82000•Water

mix»380151001

end m1xt

' * GEOMETRY

reed gecxnunit 1

3.3370E-026.6740E-02

3.3130E-02

3.3428E-026.6856E-02

ccm-"Pu Cylinder Large Bore Cask

cylindercylinder

cylinder

cylinder

end geonend dataend

1 1 5.57993 1 5.5800orig 0.00002 1 37.0760Cr19 0.00003 1 67.0760orig 0.0000

lib-4run-yes

with 12.4

68.580068.58000.0001

95.43000.0001

125.48000.0001

Input File for "!Pu in the 5 1 Cask with 8"in Table A-nitawlOSS

1SS

82 219 9

500 80 00 0

2SS 8315 100! <•.-9-

3** 9-c

•345 25000 =:352 293i.03 2.317£E-C4

3IS03

npo-5000 nfb-8000tba-60.0

inch Lead"

0.00000.0000

-26.9000

-56.9000

Lead Reflector as given

4 13200 00 0

14239 -94092 -54032300

3 10.6030 0.00001 1.007S 5.J574E-03

1 15.5994 S.3!76E»02 '94346 2930.00 1.1555E-D4

9;

1 LOCO3 10.6060 0.00001 1

! 15.9594 1.0560E-03032 293 3 1!

1 J5.5994 1.53j5£*:-3

.0079 l.!742E»041 1.000

.9719 0.0000

i ' !.•;::•

B6-22

HNF-SD-TP-SEP-063, Rev. 0KCS Basis Hero SS-2Deceiver 30. 1995Page 22

A— f2S3tend-kenova-Normal Conditions 230 g 5L Pu sphere 8" lead re f l + F*:Rreed param£r,e-200.0 lib-4" fix-yes fdn-yes npg-5000gen-120 tbe-50.0 nsk-20 nub-yes nfb-8000er.d paramread geomsphere 1 1 10.608sphere 2 1 30.528cuboid 3 1 6p72.0end seanread ffiixt•FU ISOTOPICSmix-1 54045 1.1583E-04 8015 3.3350E-02 iOOl 6.S70IE-C2

•»AT£S iSOTOPiCSmix-3 8016 3.3426E-02 1001 6.6856E-02

•LEW)mix-2 82000 3.3133E-O2

sct-1 end mixtend dataend-kenovaLoss, of Kass 450 G SL Pu sphere 8" lead re f l * F«Rread paramMe-200.0 l ib -4 f ix-yes fdn-yes nps-5000gen-120 tba-60.0 nsk-20 nub-yes nfb-8000

end paramread geansphere 1 1 10.608sphere 2 1 30.323cuboid 3 1 6p72.0

end gecaread mixt•PU ISOTOPICS

mix-1 94092 2.3176E-04 8016 3.3273E-02 1001 6.6546E.02'ViATES. 1S0TOPKS

mix-3 8015 3.3426E-02 1001 6.6856E-02•LESS

mix-2 82000 3.3133E-02sct-1 end mixtend dataend-kenovaLoss of Refl 230 g 5L .Pu sphere 12" lead re f l + P*'Rread paremtme-200.0 lifc-4 f ix-yes fdn-yes npg-5000 -cen-120 tba-60.0 nsk-20 nub-yes nfb-8000

end paramread geomsphere 1 1 10.603sphere 2 1 41.088cuboid 3 1 6p82.0

end geonread mixt'PU ISffTOPlCS

isix-l S4046 1.1568E-04 8015 3.335CE-02 1001 6.6701E-02'KATES ISOTOPICS .

tiix-3 8016 3.3428E-02 1001 6.6855E-02'LEAS

•six-2 82000 3.3133E-02s: ' .- i KiS n1xt

e"d-kenovaLoss cf Vcl i r^ 230 g 7L Pu sphere 8"lead re f l + FWSread paramtme-200.0 l i b -4 f ix-yes fdn-yes npg-5000Ser.»!20 tba-50.0 nsk-20 nub-yes fifb-8000

e-.d p=ram

s:-.i-e i I Zl.liii

cuboid 3 1 6p73.0end ceoiiread mixt•PU ISOTOPICS

rsix-1 S4032 8.0514E-05 8015 3.3374E-02 1001 6.674SE-02•KATES ISOTOPICS

r.ix-3 6315 3.342EE-02 1001 6.6S56E-02•LEO

mix-2 82030 3.3133E-02sct-1 end mixtend dataend

Input F i le for "SU i n the 5 1 Cask vrith V Lead Reflector as given inTable 4

OSS

1SS

t2SS

3"

321950000

8016•92007 .927380.0 31

52359

2S700

100182000253

.78I7E-0415.5994

2530.0 1.8909E-041

920070.0 11

15.9954253

.4092E-0415.9994

3

"o3

52235

31

3.2466E-0231

6.5227E*0231

8.7610E»02

2000

•52738

10.60801.0079

110.60801.0079

111.70001.0079

1

13

00

-52369

0.00003.5783E*03

1.0000.0000

7.1848M31.0000.0000

S.6503£«031.000

4 " f293t ' •:•

end V-:-kenova v ,Normal Condition 355 g 5L U235 73.8 g/1 sphere with 8" lead re f l •FKSread param tse-150.0 lib-4 nsk-20 gen-120 npg-5000

r-yb-yes fix-yes fdn-yes tba-60.0 nfb-8000 end paramread geometrysphere 1 1 10.608sphere 2 I 30.528cuboid 3 I 6p72.0end geomread mixt•FUEL

mix-1 52355 1.8909E-C4 8016 3.3296E-O2 1001 6.6595E-02'k'ATER ISOTOPiCSmix-3 8016 3.3428E-02 1001 6.6S56E-02•LEAD 'mix-2 82000 3.3133E-02end dataend-kenovaLoss of Kass 738 g 5L U235 147.6 g / l sphere with 8" lead re f l * FKP.read parea tme-!50.0 i*b-4 nsk-20 gen-120 npg-5000

nub-yes fix-yes fdn-yes tba-£0.0 nf&-S000 end paramread eeoraetrysphere 1 1 10.606sphere 2 1 30.923cuboid 3 ! 6P72.0end oscaread mixt•FUELmix-1 52733 3.7S17E-04 30:6 3.3J57--02 iOCl 6.6334E-02•WATER ISOTOPICS

mix-3 8015 3.342SE-02 1001 6.5555E-02'LEAOmix-2 S200S 3.3133E-C2end dataend

Less Cf ^-*: 355 = ;L "J225 72. : c ' l s?'e'S wit ' . ;2 " lead re f l + F/R

B6-23


KCS Easis Hero 96-2feeffler 30. 1955Page 23

read parani ttie-150.0 l i b -4 nsk-20 oen-120 npg-5000nub-yes f ix -yss fdn-yes tba-50.0 nft-8000 end param

' ~' gecmetryJ 1 1 10.608

sv..ere 2 1 41.083cuto^d 3 1 6pS2.0end gecmr=cd mixt•FUtL

aix-1 S236S 1.85S5t-04 6016 3.32S5E-02 1MI 6.65S5£-02•HATER ISOTOPICSnix-3 8016 3.3428E-02 1001 6.6S56E-02•LEADmix-2 82000 3.3133E-02end dataend"JtenovaLOSS of Volute 365 g 6."11 U235 55 g/L sph,e.-e with 2" Had ref : + !read param bne-150.0 l i b - 4 ' nsfc-20 gen-120 npg-5000

nub-yes f ix-yes fdn-yes tba-60.0 nfb-8000 end para^iread gectretrysphere 1 1 11.7000sphere 2 1 32.0200cuboid 3 1 6p63.0end geanread mixt•FUELnix-1 S2007 1.4092E-04 8016 3.3331E-02 1001 6.6562E-02•WATER 1S0T0PICSnix-3 8016 3.3428E-02 1001 6.6855E-02'LEAD«ix-2 82000 3.3133E-02end dataend

B6-24


Kl Basis Kew 95-ZGKKMr 33. 1995Page 24

Appendix B Input Files for Benchmark Cases given in Table 5

Input File for Pu<NOj), Sphere at 26.3 g Pu/1 with Thin Steel Shelland Full Water Reflection

Input File for Pu(KO,), Sphere at 34.3 g Pu/1 with Thin Steel Shell

Input File for Pu<N0,)4 Sphere at 35.5 g Pu/1 with 4" Concrete Shell

Input File for Pu(NOj), Sphere at 32.8 g Pu/1 with 4" Concrete Shell

Input File for Pu(S0,>, Sphere at 29.6 g Pu/1 with W Concrete Shell

Input File for 4x4 array of 93.2 wtx Enriched Uranyl Nitrate Solutionat 67.23 gUVl with concrete reflection-nitawlOSS 62 2 3 4 1319 20 9 15

1SS 500 17 0 0 00 0 6 0 00 0

t2SS 92235 92234 92235 92238 1400026000 7014 6012 8016 100120000 22000 11023 12000 1302719000 16000

3 " 92234 293 2 10.5600 0.95020.0 1.7693E-06 1 1.0079 7.5125E»051 16.1609 7.4984£*04 1 1.000

92235 293 2 10.5600 0.55020.0 1.6061E-04 1 1.0079 8.2758E*031 15.9415 8.144SE»02 1 1.000

92236 2S3 2 10.5600 0.95020.0 7.4495E-07 1 1.0079 1.7843M61 15.1622 1.7811E-05 1 1.000

92233 293 2 • 10.5500 0.95020.0 9.1432E-06 1 1.0079 1.4537£*051 15.1517 1.4502E»04 1 1.000

26000 293 1 25.4000 0.00000.0 2.5278E-04 1 1.0079 6.39396*021 15.7297 8.9763M2 1 1.000

11023 293 1 25.4000 0.00000.0 3.8303E-04 1 1.0079 5.5395E"021 15.8578 5.9671E*02 1 1.000

4 " f293tend-fcenova ROT53 4x4 array of UN solution w/o sleeve (57.28 gU/1-21.12en dies cyl)read param cefl-120 nsk-20 np9->5000 nfb-5000tne-700 .fdn-yes pit-yes run-yes tba-60.0fix-yes l ib-4 nub-yesend paramread mixt

' • KIXTKES *

"Fuel92234 1.7S53E-0692235 1.6061E-0492235 7.4455E-0792233 9.1432E-05

S01S 3.414SE-52/0!4 4.2152E-C41001 6.5I56--C2

B!X-2•Al tatt

13027 5.9i=9--02

20000 8.0213E-0326000 2.527SE-041S000 4.E976E-0414000 7.7139E-03

1001 1.0401E-0211023 3.6303E-04

80H 4.2352E-026012 6.4237E-037014 1.95SSE-0S

iSOOO 6.2509E-0522000 2.9192E-05

end inixt

•* GEOKETRY •

read gecfflun i t 1C£--"Sphere 'J23S with c'J/1-21.12 Cfl dia^i cyl) "

cylinder 1 1 . 0.505 0.00 -0.32cylinder 2 1 10.56 0.00 • -0.32cylinder 1 1 10.56 27.15 -0.32

10.55 119.1 -0.3210.96 119.1 -0.32

15.24 -15.24 15.24 -15.24 12

cylinder 0cylinder 2

cuboid 0 1unit 2

cylinder 1 1cylinder 2 1

cuboid 3 1unit 3


cuboid 0 1unit 4

cylinder 1 1cylinder 2 1cylinder 1 1cylinder 0 Icylinder 2. 1

0.5050.635

15.24 -15.24

0.5050.635

15.24 -15.24

25.4025.4015.24

0.000.00

-15.24

5.00 0.005.00 0.0015.24 -15.24

1.14 0.00 -0.3210.56 0.00 -0.3210.56 27.15 -0.3210.56 119.110.96 119.1

unit 9unit 10

cuboid 0cuboid 3cuboid 0

unit I Icuboid 0cuboid 3cuboid 0cuboid 3

unit 12cuboid 0cuboid 3 1cuboid 0 1cuboid 3 1

-0.32•0.32

-15.24

0.000.00

-15.24

1.140 5.00 0.00 •1.270 5.00 0.00

15.24 -15.24 15.24 -15.240.0 0.0 0.00.0 0.0 0.0

cuboid 0 1 15.24 -15.24 15.24unit 5

cylinder 1 1 1.14U 25.40cylinder 2 1 1.270 25.40

cuboid 3 1 15.24 -15.24 15.24unit 6


cuboid 0 1unit 7 array-1unit 8 erray-2

•ay-3 0.0 0.0 0.0

1 121.52 0.0 0.14 0.0 5.0 0.01 121.92 0.0 0.14 0.0 30.4 0.0-1 121.92 0.0 0.14 0.0 154.165 0.0

1 . 25.7 0.0 122.2 0.0 5.0 0.0'1 25.7 0.0 122.2 0.0 30.4 0.01 25.7 0.0 122.2 0.0 31.035 0.01 25.7 0.0 122.2 0.0 154.165 0.0

173.32 0.0 25.7 0.0 5.0 0.0173.32 0.0 25.7 0.0 30.4 0.0173.32 0.0 25.7 0.0 31.035 0.0173.32 0.0 25.7 0.0 154.155 0.0

unit 13 errey-4 0.0 0.0 0.0unit 14 irrs-y-5 0.0 0.0 0.0global unit 15 arrsy-5 0.0 0.0 0.0reflector 0 1 0.0 0.0 0.0 0.0 0.635 0.0 1.0reflector 3 1 0.0 0.0 0.0 0.0 25.4 0.0 1.0

r~ii arrayi-i-1 '

B6-25


»CS Basi s w » S6-2U K « e r 30. 1995Pase 25

ara-2ara-3

ara-4ara-5ara-6

nux-1 nuy-1nux-4 nuy-4 '

7 8 7 77 8 7 77 7 7 7 end ff

nux-1 nuy-3nux-3 nuy-1nux-1 nuyM3

nuz-3nuz-1

11nuz-1nuz-1nuz-1

fillfill

fillfillfill

6 547 7 7 7

!0 9 1011 13 1112 14 12

end f i l lend f i l lend f i l l

end arrayread plottt l - . 'Plot ' nch-' * ! . 'xul-0 xlr-125 yul-71.45 jlr-71.46 zul-!55 z l r - 5uax-1 wdn--l nax-130 ndn-80 lpi-10 pic-mix endend plotend dataend •

Input File for 2x2 array of 93.2 v t i Enriched Uranyl Nitrate Solutionat 76.09 gU/l with concrete reflection-nitawlOSS 82 2 3 4 18

19 20 9 • 151SS 500 17 0 0 0

0 6 0 0

92236 92233 140008015 1C01

12000 13027

0 0t2SS 92235 92234

26000 7014 601220000" 22000 1102319000 16000

3** 92234 293 2 10,5500 0.95020.0 2.0009E-06 1 1.0079 6.6236E*051 16.1816 6.6870E*04 1 1.000

92235 293 2 10.5600 0.9502,<--0.0 1.8164E-04 1 1.0079 7.2963E-03•: "fvl 15.9352 7.2503E*02 1 1.000•••..i36 293 2 10.5600 0.9502

0.0 8.4250E-07 1 1.0079 1.5731E*051 16.1829 l.S883E»05 1 1.000

92238 293 2 10.5600 0.95020.0 1.0341E-0S 1 1.0079 1.2816E-051 16.1712 1.29301*04 1 1.000

26000 293 1 25.400 0.00000.0 2.5276E-04 1 1.0079 8.3939E»021 16.7297 8.9763E»02 1 1.000

11023 293 1 25.400 0.00000.0 3.8303E-04 1 1.0079 5.53S5E*02 •1 16.8578 5.9S71M2 1 1.000

4 " f293tend-fcenovaR0T54 2x2 array w/o sleeve {76.09 gU/1-21.12 cm diamcyl)read param gen-120 nsk-20 r.pg-5000 nfb-8000tme-700 fdn-yes pit-yes run-yes tba-50.0fix-yes l ib-4 nub-yesend paramread mixt

•• MIXTURES

n-.ix-''Fusl

5223492235=2235" 2 3 3

'15014

1001mix-2"Al t a r*

13027rix-3•Cccrs-.e

* .

2.000SE-C-S1.E164E-048.4250--071.C34SE-053.424SE-024.7215E-046.4955E-02

5.9-J5E-52

120001302720000

• 2600019000140001001

11023801660127014

1500022000

end mixt

7.1685E-041.1241E-038.0213E-032.5278E-044.8976E-047.7135E-031.0401E-023.6303E-044.23S2E-026.4237E-031.9958E-058.2809E-052.9192E-05

' * GECMETSY

read georaunit 1cylinder 1cylinder 2cylinder 1cylinder 0cylinder 2

cuboid 0unit 2cylinder 1cylinder^

cuboid 3unit 3cylinder 1cylinder 2

cuboid 0unit 4cylinder 1cylinder 2cylinder 1cylinder 0cylinder 2



cuboid 0unit 7 arunit 8 arunit 9 arunit 10

cuboid 0cuboid 3cuboid 0

unit 11cuboid 0cuboid 3cuboid 0

unit 12cuboid 0cuboid 3cuboid 0cuboid 3

unit !3cuboid 0cuboid 3cuboid 0cuboid 3

ur.it 14 erunit 15 a.-ur.it 15 erS'.cbal m i ;

0.505 0.00 -0.3210.56 0.00 -0.3210.56 62.34 -0.3210.55 119.1 -0.3210.96 119.1 -0:3215.24 -15,24- 15.24 -15.24 123.445 -0.32

1 0.505 25.40 0.001 0.635 25.40 0.001 15.24 -15.24 15.24 -15.24 25.4 0.0

1 0.505 5.00 0.001 0.635 5.00 0.001 15.24 -15.24 15.24 -15.24 5.0 0.0

1 1.14 0.00 -0.321 10.55 0.00 -0.321 • 10.56 62.34 -0.321 10.55 119.1 -0.321 10.96 • 119.1 -0.321 15.24 -15.24 15.24 -15.24 123.445 -0.32

1 1.140 25.40 0.001 1.270 25.40 • 0.001 15.24 -15.24 15.24 -15.24 25.4 0.0

'1 1.140 5.00 0.001 1.270 5.00 0.001 15.24 -15.24 15.24 -15.24 5.0 0.0

ray-1 0.0 0.0 0.0ray-2 0.0 0.0 0.0rey-3 0.0 0.0 0.0

1 30.48 0.0 60.96 0.0 5.0 0.01 30.48 0.0 60.96 0.0 30.4 0.01 30.48 0.0 60.96 0.0 154.155 0.0

1 121.92'0.0 30.62 0.0 5.0 0.01 121.92 0.0 30.62 0.0 30.4 0.01 121.92 0.0 30.62 0.0 154.155 0.0

1 25.7 0.0 122.2 0.0 5.0 0.01 25.7 0.0 122.2 0.0 30.4 0.01 25.7 0.0 122.2 0.0 31.035 0.0I 25.7 0.0 122.2 0.0 154.155 0.0

173.32 0.0 25.7 0.0 5.0 0.0173.32 0.0 25.7 0.0 30.4 0.0173.32 0.0 25.7173.32 0.0 25.7 0.0

iy-4 0.0 0.0 0.0ray-5 0.0 0.0 0.0

:y-5 0.0- 0.0 0.0arrav-7 0.0 0.0 0.0

0.C 0.0 5.0 0.0 C0.0 0.0 0.0 0.0 2-

0.0 31.035 0.0154.165 0.0

B6-26


KCS Basis Keno S6-2DKKt.er 30. 1955Page 26

end geom

•* A W V *

read arrayara-1 nux-1 nuy-1ara-2 nux-1 nuy-1arc-3 nux-2 nuy-2ars-4 nux-3 nuy-1cf£-5 nux-2 nuy-3ere-6 nux-3 nuy-1era-7 nux-1 nuy-3end arrayread plott t l - 'P lo t * • nch-' * !

nyz-3nuz-3nu2-ln-j2-lttUZ-1nuz-1nuz-1

fillfillfillfillfillfillfill

picmix

3 2 16 5 48 7 3710 5 1011 14 1112 15 1213 15 13

end f i l lend f i l lend f i l lend f i l lend f i nend f i l lend f i l l

xul-25. xir-73 yul-71.45 ylr-71.45 2ul-165 z l r - 1iax-3 wdn-1 nax'UO ndr,-S0 lpi-10 endend- plotend dataend

Input File for 4x4 array of 93.2 wtx Enriched Uranyl Nitrate Solutionat 360.37 gU/1 with concrete reflection•nitawlOSS 82 2 3 4 18

1SS195000 00 0

20 9

23 0 0 0

15

t2!S 92235 92234 92236 92238 14000

26000 -26001 6012 6016 100120000 22000 11023 12000 1302719000 16000 15031 25055 42000

• 7014 24000 280003** 92234 293 2 8.3S00 0.6576

0.0 9.4767E-06 1 1.0079 1.2499E*051 16.7021 1.8007E*04 1 1.000

92235 293 2 8.3300 0.65760.0 8.6027E-04 1 1.0079 1.3769E*031 15.7583 1. S67SE-02 1. 1.000

92236 293 2 8.3800 0.65760.0 3.9902E-06 1 1.0079 2.968SE*0S1 16.7073 4.2781E»04 1 1.000

92238 293 2 8.3800 0.6576. •0.0 4.8974E-05 1 1.0079 2.4186Ei041 16.6623 3.4759E»03 1 1.000

26000 293 1 25.4000 0.00000.0 2.5278E-04 1 1.0079 8.3939E*021 16.7297 8.9.763E-02 1 1.000

11023 293 1 25.4000 0.00000.0 3.8303E-04 1 1.0079 S.5395E+021 16.8578 S.5S71E»02 1 1.000

25001 2S3 1 0.3100 0.00000.0 5.9852E-02 1 .58.69 2.2046E*001 48.1197 4.0995E-02 1 1.000

25055 293 1 0.3100 0.00000.0 1.1209E-03 1 55.847 6.0S72E*021 54.2180 3.6440E-02 1 1.000

24000 293 1 0.3100 0.00000.0 l.eSSH-ta 2 55.84; 4.0172£*021 55.4EG0 3.5621E-02 1 1.000

28000 293 1 0.3100 0.00000.0 7.5400E-03 1 E5.847 9.0492E»011 48.1157 4.C5S5E-02 ! 1.000

4 " f253te.-d-kenovaS0T51 4x4 array US solution w/sleeve (350.37 oU/1-15.12 cread paren cen-120 nsk-20 npc-5000 nfD-S000tT^-700 fc*n-yes pit-yes rur.-yes tb=-50.0fix-yes l ib-4 nuS-yes

3 cyl)

' • K1XTU3ES •

nix-1•Fuel

92234 9.4757E-0592235 8.6027E-0492235 3.5S02E-0592233 4.S974E-05£3!S 3.72S5E-0270i4 2.1977E-031001 5.8064E-02

mix-2•Al tank

13027 5.S459E-02«1x-3•Steel Sleeve

•25001 5.9S52E-0224000 1.69SSE-022600O 7.5400E-036012 2.6231E-04

14000 1.3768E-0315031 3.8530E-0516000 2.82S2E-0525055 1.1209E-0342000 8.9553E-06

fflix-4'Concrete

12000 7.1385E-0413027 1.1241E-03200CO 8.0213E-0326000 2.5278E-0419000 4.6976E-0414000 7.7139E-031001 1.0401E-02

11023 3.8303E-048015 4.2362E-026012 6.4237E-037014 1.955SE-05

16000 8.2809E-0522000 2.9192E-05

end raixt

'* GEOKETBY •

read seenunit 1

cylinder 1 1cylinder 2 1cylinder 1 1cylinder 0 1cylinder 2 1cylinder 0 1cylinder 3 1

0.5058.068.058.068.338.388.69

0.00 -0.320.00 -0.32

32.32119.1119.1121.68121.68

cuboid 0- 1 15.24 -15.24 15.24unit 2


- 0'. 5050.635

25.4025.40

cuboid 4 1 15.24 -15.24 15.24unit 3


0.5050.635

-0.32-0.32•0.32•0.32-0.32

-15.24 123.445 -0.32

' 0.000.00

-15.24 25.4 0.0

5.00 0.005.00 0.00

cuboid 0 1 15.24 -15.24 15.24unit 4

cylinder ! 1cvlinde.- 2 1cvl-.ncer i 1cylinder 0 1cylinder 2 1cylinder 0 1cylinder 3 1

cuboid 0 1 15.

cylinde- : 1cylinder 2 i

1.143.058.068.068.338.338.69

24 -!:

' '401.27G

0.00 -0.32

-15.24 5.0 0.0

0.00 -0.3232.32119.1119.1121.63121.68

5.24 15.24

25.4325.40

•0.32-0.32•0.32-0.32-0.32

-15.24 123.445 -0.32

0.00O.CD

B6-27


KCS Basis Meso 96-2DeceSer 30. 1595 •Page 27

cuboid 4 1 15.24 -15.24 15.24 -15.24 25.4 0.0unit 6

" ' i n t e r 1 1 1.140 5.00 0.00nder 2 1 1.270 5.00 0.03

cuboid 0 1 15.24 -15.24 15.24 -35.24 5.0 0.0unit 7 array-1 0.0 0.0 0.0unit's array-2 0.0 0.0 0.0unit 5 array-3 0.0 0.0 0.0unit 10

cuboid 0 1 121.92 0.0 0.14 0.0 5.0 0.0cuboid 4 1 121.52 0.0 0.14 0.0 30.4 0.0cuboid 0 1 121.92 0.0 0.14 0.0 154.165 0.0

unit 11

1 34.0419 6.1400M1 1 1.00024000 293 2 0.70735 0.0000

0.64135 1.0904E-04 1 26.98154 7.4309M21 35.0663 6.013iE-0! 1 1 000

4 " f293tend-ksnova4.31 k t ! l>02 rods P-2.54 ca (Opt foe1) lead ref lector S 0.00 Inread paraatae-700 oen-120 nsk-20- • l ib-4 npg-5000fix-yes fdn-yes tba-50.0 nub-yes nfb-8000run-yes end param

cuboid 0cuboid 4cuboid 0ci£oid 4

unit 12cuboid 0cuboid 4cuboid 0cuboid 4

1 25.71 .25.71 25.71 25.7

1 173.321 173.321 173.321 173.32

0.0 122.2 0.0 5 0 0.00.0 122.2 0.0 30.4 0.00.0 122.2 0.0 31.035 0.00.0 122.2 0.0 154.165 0.0

0.0 25.7 0.0 5.0 0.00.0 25.7 0.0 30.4 0.0-0.0 25.7 0.0 31.035 0.00.0 25.7 0.0 154.155 0.0

unit 13 array-4 0.0 0.0 0.0unit 14 arrglobal unit 15reflector 0reflector 4end geom

•* ARRAY *

read arrayara-1 nuxara-2 nux

ay-5 0.0 0.0-0.0array-5 0.0 0.0 0.0

1 0.0 0.0 0.0 0.0 0.635 0.0 1.01 0.0 0.0 0.0 0.0 25.4 0.0 1.0 '

- ! nuy-1•1 nuy-1

er-v?3 nux-4 nuy-4wara-4 nvx •1 nuy-3ara-5 nux-3 nuy-1ara-6 nux-1 nuy-3end array •read plott t l - ' P l o t ' nchxul-0. x!r-150uax-1 wdn—1end plotend dataend

naz-3 f i l l 3 2 1nuz-3 f i l l 6 5 4nuz-1 f i l l 7 7 7 7

7 8 7 77 8 7 77 7 7 7 end

ma-1 01) 10 9 10 end

end f i l lend f i l l

f i l lf i l l

r.uz-1 f i l l 11 13 11 end f i l lnuz-1 f i l l 12 14 12 end

•' * ! . ' p ic iaixyul-71.45nex-130

ylr-71.45 zul-165 z l r - 3ncn-SO lpi-10 end

f i l l

Input File for 4.31 wU Optiimjm Moderated U0, Rods with Lead Reflectorat Various Distances-nitavlOSS 82

19-SS 500

00

t2SS 92235

!001140002505545D00

; • * 52235CO

92233CO t

125001

0.641351

250010.54135

22021

00

92233220001600012000

253.K24E-C3233.C5IB

293.21935-02235.0435

2532.0305E-04

3J.4S24253

IClrTi-'i

3 49 150 0

5 0

13027 82000-25001 2503024000 2000017000 22000

2

2.3237E-C221

5.3372E-C!21

2.3202E-0i2

.63255.9954

1.53255.9554

1.707355.93154

1.70735- ci"4

18

0

0

8016-25001

70146012

0.0—091.6SS0E-32

1.0000.0405

7.745SE-001.0000.0000

3.52C6E-021.0000.0000

7.5i53i-02

' * KIXTU3-S *• *******************reed mixt sct-1•Fueli»1x-l

92235 1.0124E-03• 92238 2.2193E-02

6015 4.6411E-02'Cladraix-2

' 13027 5.7378E-02140C0 2.3072E-0426001 2.0305E-0429001 1.0197E-04

25055 4.4230E-05120OO 7.9981E-04

24000 1.0904E-0422300 5.072SE-05

'Watermix-3

8015 3.3428E-02100! 6.6656E-02

17000 5.1298E-0726000 3.2350E-10 •82000 1.4532E-1148000 3.2144E-11

7014 4.0792E-09'Lead151 x-4

82000 3.2771E-0229000 1.3509E-04

"Rubber End Capsmix-5

60!2 3.8415E-021001 5.1304E-02

20000 2.2527E-0315030 4.2183E-0480!6 1.0589E-02

14000 8.4975E-05end mixt

' * GEKTRY •

read gemunit 1car.-"Sinole Fuel Pin"

cylinder 1 1 0.63245cylinder 0 1 0.64135cylinder- 2 1 0.70735cylir-isr- 5 1 0.70735

c.i:1« 3 1 1.270 -1.270g r i t 2 sr-ray 1 -10.15CCT.-"i3 x 5 array of pins"unit 3c&T.-"Crit1C51 Separation - Witer Gap"

ciosfj 3 1 2P10.150clotal u ' i t 4 array 2 0 0 0'inr.er s'nell for lead

cuio'S 3 1 20.320 0.00•D.;sr- i-C\ -o f'.V: »itn H i i

•:-•:•:•; i 1 30.52 -ID.20

9!.4491.4491.4493.S3

1.2"0 -1.270-16.51

2P10.310

152.15 -11.65

152.15 -11.£5

000

-2.5423.93 -2.54

-2.=4

93.93 -2.54

107.42 -15.93

1C7.42 -J5.53

B6-28


h'CS Basis Keroo 96-2December 30. 1956

'Water tankcvhoid 3

end aeon

read arrayera-1 nux-8 nuy-13 nuz-1era-2 nux-1 nuy-S nuz-1

50.82 -30.50 170.SO -30.50 223.54 -30.59

f i l l lO4rl t end f i l lf i l l 2 3 2 3 2 t -end. f i l l

cu&oio 3 1 20.S6Q -0.66 152.31 .11.69 107.42 -15.SS'Gutsr shell to f i l l with lead

cuboid 4 I 31.18 -10.85 152.31 .-11.69 107.42 -15.S3'Water t=r,k

cubcid 3 1 50.82-30.50 171.12-30.50 121.54-30.50end gsc.7i

end amer.d datend-kenova4.31 wtread patme-70(f1x-yesrun-yes

aya

S UO2 rods P-2.54 cm (Opt Mod) lead reflector t 0.25 inram

gen-120fdn-yesend parem

*************•* FUTURES *

read mi'Fuel

mix-1

'Cladmix-2

'Watermix-3

•Leadnlx-4

•Rubbernix«5

end mixt

•* GEOKE

«t sct-1

92235 1.0124E-0392238 2.2193E-028016 4.6411E-02

13027 5.7878E-0214000 2.3072E-0425001 2.0305E-0429001 1.0197E-0425055 4.4230E-0512000 7.9981E-0424000 1.0904E-0422000 5.0729E-06

8016 3.342SE-021001 6.6856E-02

17000 5.1258E-0725000 3.2350E-1082000 1.4532E-1148000 3.2144E-U

7014 4.0792E-09

82000 3.2771E-0229000 1.3909E-04End Caps

6012 3.S415E-021001 5.1304E-02

20000 2.2627E-0316000 4.2183E-048016 1.09S9E-02

14000 8.4975E-05

TRY •************

read gs&njnit 1corVSingie Fuel Pin"

c v n

cyli

CvV

nder 1ncer 0r.der 2nder 5

CtAetfd 3jai t 2COT.-"13^•; t 3

; : » ^

arrayx 8 arra >• of pins

nsk-20 . 11b-4 npg-SOOOtba-50.0 nub-yes nfb-8000

0.63245 91.44 00.54135 51.44 o0.70735 91.44 00.70735 93.95 -2.54

1.270 -1.270 1.270 -1.270 93.93 -2.54-10.15 -15.51 -2.54

cc 's '""

read arrayara-1 nux-3 n-y-13 nuz-1ara-2 nux-1 nuy-5 nuz-1end arrayend dataend-kenova

f i l l !04rl tf i l l 2 3 2 3

end f i l l2 t end f i l l

4.31 wtS UC2 rods P-2.54 cm (Opt Mod) lead ref lector 0 0.52 inread paraafcre-700' oen-120fix-yes fcn-yesrun-yes end paramI*******************

' * MIXTURES *

read mixt sc t -1•Fuelmix-1

92235 1.0124E-0392233 2.2193E-028015 4.6411E-02

•Cladmix-2

13027 5.7878E-0214000 2.3072E-0425001 2.0305E-0429001 1.0197E-0425055 4.4230E-0512000 7.9981E-0424000 1.0904E-0422000 5.0729E-05

'Watermix-3

E0i5 3.3428E-02100! 6.6856E-02

17000 5.129SE-0726000 3.2350E-1082000 1.4532E-114SSO0 3.2144E-H7014 4.0792E-09

"Leadmix-4

82000 3.2771E-0225000 1.3909E-04

'Rubber End Capstnix-b

6012 3.6415E-021051 5.1304E-02

20000 2.2627E-0315000 4.2153E-04

60i5 1.0935E-0214500 8.4575E-05

end mixt

' • C-ECKETSY •' * * * * * * * * * . * * * * * * * * *

r=sd cepnunit 1ccc?-"Sin=;e Fuel ?'.ir

cvlir.:ar 1 Icylinder 0 1cylinder 2 1cylinder 5 1

cubrc 3 1

CD~-"!3 X £ array cf pins

nsk-20 l i b -4 npg-5000tba-60.0 nub-yes nfo-6000

0.632450.64135

• 0.707350.70735

1.270 -1.270 1.270

-10.15

91.44 C51.44 f51.44 053.98 -2.54

-1.270 53.98 -2.54

B6-29


50.82 -30.50 170.80 -30.50 121.54 -30.50

KCS Basis nax> 96-2D*c**er 30. 19S5Page 2B

'Water tankcuboid 3 1

end ceOT

reed arrayera-l nux-8 nuy-13 nuz-1sre-2 nyx-1 nyy-5 nuz-1end arrayer.d dstaend-kenova4.31 wtS U02 rods P-2.54 cm {Opt Hod) lead reflector 9 0.25 inread paramtn-ie-700 gen-120 nsk-20 1 i b-4 npg-5000fix-yes fdn-yes tba-60.0 nub-yes nfb-50G0run-yes end parsffl

f i l l 104rl t end f i l lf i l l 2 3 2 3 2 t end.f i l l

"" BiXTlRES *

read mixt sct-1"fuelmix-1

'Cladmix-2

"watermix-3

'leadmix-4

92235 1.0124E-0392238 2.2193E-028016 4.6411E-02

13027 5.7878E-0214000 2.3072E-0426001 2.0305E-04 •29001 1.0197E-0425055 4.4230E-0512000 7.9931E-0424000 1.0904E-0422000 5.0729E-05

8016 3.3423E-021001 6.6855E-02

17000 5.12S3E-0726000 3.2350E-1O82000 1.4532E-1148000 3.2144E-U

7014 4.07S2E-09

82000 3.2771E-0225000 1.3S05E-04

'Rubber End Capsmix-5

end mix

6012 3.8415E-021001 5.1304E-02

20000 2.2527E-0316000 4.2133E-048016 1.0939E-02

14000 8.4975E-05

"* GECME7.W *

unit 1ca~-"Sir

cAcv'cylcyl

ale Fuel Pin"nder 1 !

ncr.i

cubeunit 2CO---13IT1'." ^COT.-"Cr

c

X

-.-

ar 0 1er 2 1ar 5 !id 3 1 "1array 15 array of pins"

cal Se:araticn -id 3 't V :.7!y 2 o

0.53245 51.440.54135 91.440.70735 91.440.70735 S3.S3

270 -1.270 1.270 -1.270•10.16 ' -15.51

Water Gap"2310.150 2?!0.3900 0

000

-2.54-2.54-2.54

f i l l 104rl fend f i l lf i l l 2 3 2 3 2 t end f f i l

cuboid 3 1 20.980 -0.66 152..31 -11.69 107.42 -15.58"Outer shell to f i l l with lead

cuboid 4 1 31.18 -10.86 152.31.-11.69 107.42 -15.5S"Water tank

cuboid 3 1 50.82 -30.50 171.12 -30.50 121.94 -30.60end cecffl

read arrayerc-i nux-3 ruy-13 nuz-1cTc-2 nux-l nuy-5 nvz-1end arrayend dataend-kenova4.31 «8 U02 rods P-2.54 csi (Opt Kod) lead reflector G 0.52 inread paramtse-700" oen-120 nst-20 . l ib-4 nps-5000fix-yes fdn-yes tba-60.0 nub-yes nfb-3000run-yes end param

"• MIXTURES •

"Fuelmix-1

•Cladmix-2

92235 1.0124E-0392238 2.2193E-028015 4.64UE-02

13027 5.7878E-02 '14000 2.3072E-0426001 2.0305E-0425001 1.0197E-0425055 4.4230E-0512000 7.9981E-0424000 1.0904E-0422000 5.0729E-05

'Watermix-3

6015' 3.3428E-02. 1001 6.6856E-02

17000 5.12S8E-0726000 3.2350E-1082CC0 1.4S32E-1145000 3.2144E-117014 4.0792E-09

'Lead • •mix-4

82000 3.2771E-0229000 1.3909E-04


60:2 3.8415E-021001 5.1304E-02

20000 2.2627E-0315000 4.2183E-045016 1.0989E-02

14000 8.4975E-05end mixt

•• KWETRY -

read cexiunit 1coi--Sin=!e Fuel Pin"

cylinKr i 1cylinder 0 1cylinder 2 1cylinder 5 I

cuboid 3 1•j'M 2 srray 1COT.-"13 x 5 array of pins"ur/.t 3co--"Crit"cel Separation

0.63245 91.44 00.64135 91.44 C

" 0.70735 SI.44 00.70735 S3.98 -2.54

1.270 -1.270 1.270 -1.270 93.98 -2.54•10.15 -15.51 -2.54

Water Gap"

B6-3O


NCS Basis H K O 9S-2Oe:s.Tisr 30. 1SS5Page 29

cuboid 3 1 2pl0.160 2p3.520 93.53global unit 4 array 2 0 0 0•"" -r shell for lead

cuboid 3 1 21.641 -1.32 150.57 -13.43 107.42X-^er shall to f i l l with lead

cuboid 4 1 31.64 -11.52 150.57 -13.43 107.42•'niter tank

cuboid 3 1 50.S2 -30.50 167.64 -30.50 121.54er;d ceom

read arrayara-1 nux-8 nuy-13 nuz-1ara-2 nux-1 nuy-5 nuz-1end arrayend dataend

15.S3

15.93

30.50

f i l l 104rl t end f i l lf i l l 2 3 2 3 2 t end f i l l

4.31 «S U02 rods f-2.54 cm (Opt Kcread paramtms-700 gen-120 nsk-20fix-yes fdn-yes tba-60.0run-yes end param

•• KIKTURES •

) lead reflector ? 2.13 in

1ib-4nub-yss

npg-5000nfb-80C0

read mixt sct-1'Fuelmix-1

92235 1.0124E-0392238 2.2193E-028016 4.6411E-02

•Cladir,ix-2

'Waterrsix-3

13027 5.7878E-0214000 2.3072E-0426001 2.0305E-0429001 1.0197E-0425055 4.4230E-0512000 7.9981E-0424000 1.0904E-042-2000 5.0729E-05

8016 3.3428E-021001 6.6855E-02

17000 5.12S8E-0726000 3.2350E-1082000 1.4532E-1148000 3.2144E-11

7014 4.0752E-09'Leadmix-4

82000 3.2771E-0225000.1.3909E-04


6012 3.E415E-021001 5.1304E-02

20000 2.2627E-0316000 4.2163E-046015 1.05S9E-02

14000 8.45;5E-05

. f i l l lMrl t end f i l lf i l l 2 32 3 2 tend f i l l

ccc-"i3 x 8 array of pins-unit 3cor.-"Critical Separation - Water Gap"

cuboid 3 1 2pl0.150 2p5.150 93.98 -2.54global unit 4 array 2 0 0 0'Inner shell for lead

cuboid 3 1 25.725 -5.41 141.63 -22.17 107.42 -15.95'Outer snell to f i l l with lead

cuboid 4 1 35.53 -15.61 141.83 -22.17 107.42 -15.93'Water tank

cuboid 3 1 50.82 -30.50 150.15 -30.50 121.94 -30.50end cean

read arrayara-1 nux-3 nvy-13 nuz-1are-2 nux-1 nuy-5 nuz-1end arrayer.d dataend-kenova4.31 wts U02 rods P-2.54 cm (Opt Hod) without lead reflectorread peramose-700 sen-120 nsk-20 l ib-4 npo-5000fix-yes fdn-yes tba-60.0 nub-yes nfb-8000run-yes end param —

'• MixllRES •

read mixf sct-1'Fuelmix-I

52235 1.0124E-0352238 2.2193E-028015 4.64UE-02

•Cladmix-2

'Watermix-3

1302? 5.7878E-0214000 2.3072E-0426001 2.0305E-0425001 1.0197E-0425055 4.4230E-0512003 7.9S81E-0424000 1.0S04E-0422000 5.0729E-05

8015 3.342SE-021O01 6.6855E-0217000 5.1298E-0725000 3.2350E-1082000 1.4532E-1148000 3.2144E-117014 4.0752E-09

"Leadmix-4

82000 3.2771E-0229000 1.3905E-04

'Rubber End Caps

5012 3.6415E-02100! S.1304E-02

20000 2.2627E-0315000 4.2183E-045015 1.0939E-0214000 3.4975E-05

singlecylindercylindercylindercylinder

2 er

Fuel Fin"1 10 12 15 I• I 1.270

0.632450.64135C 707350.70735•1.270 1.270-10.15

51.4451.4451.4453.53

-1.2^0 53.55

000

-2.54-2.54•2.54

mi ceo'nunit !co=--S:n;'e

cv'irce

-v>i—-

?uelr 1

r 0

- 2

pin"11i

0.632453.54:350.70735

51.445i.4491.44

B6-31


KCS Basis Hero 96-2Decetoer 30. 1996Page 30

cylinder 5 1 0.70735 93.98 -2.54cuboid 3 1 1.270 -1.270 1.270 -1.270 93.93 -2.54

unit 2 array 1 -10.16 -16.51 -2.54ccm-"13 x 8 array of pins"unit 3cotrVCritical Separation - Water Gap"

cuboid 3 1 2?10.160 2p4.120 .93.95 -2.54global unit 4 array 2 0 0 0"Water tank

Cuboid 3 1 50.S2 -30.50 146.04 -30.50 121.94 -30.50end gecm

read arrayara-1 nux-8 nuy l3 nuz-1era-2 flux-1 nuy-5 nuz-1end arrayend dataend

f i l l 104rl t end f i l lf i l l 2 3 2 3 2 t end f i l l

Input Fi le for 4.31 wt* Undenroderated U02 Rods with Lead Reflector a tVarious Distances

' LEAD UALL ISOTOPICSnix- 4

62000 3.2771E-022S0OO 3.9239E-04

end fiixt

SETUP GEOMETRY

12X15 PI» LATTICE

unit. 1COT,-" UNIT PIN CELL •cylinder 1 1 0.63245 92.075 0.0cylinder 0 1 0.64135 92.075 0.0cylinder 2 1 0.70735 92.075 0.0cuboid 3 1 0.945 -0.946 0.946 -0.946 92.075 0.0

.OSS

1SS

t2SS

3 "

4**

end-keno5

8219

50000

9223492235253041302725000

2350.0

1233CO

1f293.16

29

2400

2505524304290001200023000

293.160.0010104

31502

9223592238420005010

4030221

238.049392 232.5850528293.15

0.0221621

235.043971 0.538340131

SIMULATED SHIPPING CONTAINER EXP- - 4 . 3 1 \ m FUELread pararaeterstra-290.0 tba-50.0 cen-120 npg-5000 1fix-yespit-yesend par

fdn-yes nub-yes pwt-yesrun-yes nsk-20

araeters

iib-4

42000

-235-238

283045011

820000.63245 0.15.9994 171

1-0.63245 0.

18

00

80161001

14000' 24000

18049495..4236421

118049496

15.9994 7.8161754511

LEAD REFL

1

(nps-5000)

un i t 2 array 1 -11.352 -15.136 0.0c m - " 12X16 PI.N ARRAY (ASSEM3LY >'-cuboid 3 1 11.35201 -11.35201 15.13601 -15.13601 92.075 0.0

u n i t 3ceo-" CRITICAL SEPARATION WATER GAP • •cuboid 3 1 11.35201 -11.35201 8.87 -8.67 92.075 0.0

global un i t 4 array 2 0.0 0.0 0.0c m - " CRITICAL ARRAY GEOMETRY (3 ASSEMBLIES) "•INNER CU5OID SHELL FOR LEADcuboid 3 1 22.70402 -0.00002 145.148 -18.852 105.56 -17.84•OUTER CU30I0 SHELL TO FILL K/LEAOcuboid 4 1 32.90402 -10.20002 145.148 -18.852 105.55 -17.84•CUSOID OF HATER TANScuboid 3 1 53.20401 -30.501 170.878 -54.122 107.275 -17.84end seonetry

read arrayara-1 nux-12 nuy-16 nuz-1 f i l l 192rl t end f i l lara-2 nux-1 nuy-5 nuz-1 f i l l 2 3 2 3 2 t end f i l lend arrayread start nst-1 end start

SETUP MIXTURES

rsed rnixt sct-11 FUEL ISOTOPICS

92234235

92236238

S016

5.1843E-051.0104E-035.1403i-052.2160E-024.6762E-02

' CLAO ISOTOPICSsix - 2

13027120001400024000250552600029000

5.E075--025.34S7E-044.63:SE-041.C942--044.43S1E-C52.0374E-041.0233E-C4

• KSESATCS ISOTC=:CSsix- 3

8515100!

3.3:-;=E-C25.5737E-02

read plot

t t l - ' XY PIS CELL SY MATERIAL'nch«* o:-1

xul-0.0 xlr-1.892 yul-l.S92 ylr -0.0 zul-50.0 zlr-50.0uax-1.0 vdn--1.0 nax-80 lpi-10 p ie t is t end

t t l - 1 XY SECTION OF 12x15 ASSEMBLY BY MATERIAL'ncn-' 00-'xul-3.0 xlr-22.'704yul-30.272ylr-0.0 zvl-50.0 zlr-50.0uax-l.G vcr.—!.O nex>-100 lpi-10 pic^r;=t e.id

t t l - 1 XY SECTION Of CRniWl A^s« 5Y KAT£SIAL'nch-' OD-*'xul —15.0 xir-35.0 yul"140.0 y l r - -5 .0 zul-50.0 zV-50.0ucx-1.0 vtfn--1.0 nax-100 lpi-10 pic-TiSt end

t t l - ' X2 StCTiOV Or CRITICAL ASSAY BY KA7ESIAL'ncfi-' oo-*'x- j l -15.0 xlr-35.0 yai-1.27 ylr-1.27 2u>sO.O z i r - IO.Oyjx-i.O W-.--1.0 nax-100 lpi-10 :ic-G£t end

B6-32


KS Easis Kew S6-2Ds=«»er 30. 1995Page 31

er.d plotend data

s-wiated shipping container exp - 4.31 wt? fuel lead refl (np=-5000)read parameterstfie-290.0 tba-50.0 gen-120 nsk-20 npg-5000 lib-4fix-yes fdn-yes nub yes pwt-yesp':-yes run-yesend parameters

setup mixtures

'cuboid cf water tankcuboid 3 1 53.20401 -30.501 170.£78 -54.122 107.275 -17.84end ceaiietry

re=d arrayara-1 nyx-12 n-jy-16 nuz-1 f i l l l«2r! t end f i l lara-2 nux-1 nay-S nuz-1 f i l l 2 3 2 3 2 t end f i l lend arrayread start r.st-1 end start

read ntixt sct-1" fuel isotopicsrcix- 1

92234 5.1843e-06235 1.0104e-03

92235 5.1403e-05235 2.216Ce-02

£016 4.6752e-G2- dad isotopicsmix- 2

13027 5.S075e-0212000 5.3487e-0414000 4.6300e-0424000 1.0942e-0425055 4.43Sle-0525000 2.0374e-0429000 1.0233S-04

' moderator isotopicsmix- 3. :- 6016 3.3369S-02..-.-.• 1001 6.6737e-021 v.jd wall isotopicsmix- 4

62000 3.2771e-0229000 3.9239e-04

end mixt

setup geometry

12x15 pin latt ice

read plot

t t l - ' xy pin cell by materiel'nch-' o:- 'xul-0.0 xlr-1.892 yul-1.892 ylr-0.0 zul-50.0 zlr-50.0ucx-1.0 vdn—1.0 nax-SO lpi-10 pic-mat end

t t l - ' ' xy section of 12x15 assembly by material"nch-" oo-'1

xul-0.0 xlr-22.704 yul-30.272 ylr-0.0 zul-50.0 zlr-50.0uax-1.0 vdr.--1.0 nax-100 lpi-10 pic-mat end

t t l - ' xy section of cr i t ical array by material'rich"' oo-*' •xyl-15.0 xlr-35.0 yul-140.0 y l r - 5 . 0 2U1-50.0 zlr-50.0uax-1.0 vdn--1.0 nax-100 lpi-10 pic-mat end

t t l - ' xz section of cr i t ica l array by material'nch-* co-*"xul-15.0 xlr-35.0 yul-1.27 ylr-1.27 zul-50.0 z l r -10.0uax-1.0 wdn—1.0 nax-100 lpi-10 picnnat endend plotend dataend-kenc5Simulated shipping container exp -4.31v.tS fuel lead refl 93 cm (5000)read parameterstne-290.0 tW-60.0 gen-120 nsk-20 npg-5000 l ib-4fix-yes fdn-yes nub-yes' pwt-yespit-yes run-yesend parameters

unit 1con:-" unit pin cell "cylinder 1 1 0.63245 92.075 0.0cylinder 0 1 0.54135 92.075 0.0cylinder 2 1 0.70735 92.075 0.0Cuboid 3 1 0.S46 -0.946 0.946 -0.945 92.075 0.0

ar.it.2 array 1 -11.352 -15.135 0.0car,-" 12x15 pin array (assembly)"cuicid 3 1 11.35201 -11.35201 15.13501 -15.13601 92.075 0.0

re it 3COT.-" critical separation water cap "c^-.ii 3 i 1I.352C1 -11.35201 3.715 -S.715 52.075

o^o^sl unit 4 array 2 0.0 0.0 0.0COT:-" cr i t ical array ceccetry (3 esseaalies) "-'.--=r cyboid sr.ell fcr leadCJt-cod 3 1 24.cS -1.955 1^5.1*3 -15.352 105.55 -17.' :-:=r CUSDIS sr.?":" :o f*":! w/lssc:•-::•:; 4 j 34.55 -12.ZU 1^5.1-6 -15.S52 105.56 -17.e

read mixt • sct-1' fuel isotopicsmix- 1

92234 5.1843e-05235 1.01C4e-03 "

92235 5.1403e-06"233' 2.2160e-02

8015 4.6762e-02" clad isctcpicsnix- 2

13027 5.£0756-0212000 5.3487e-C4liOC-3 4.5300e-0424000 1.0W2e-0425055 4.i3Sle-052:0C0 2.G374e-C425050 1.02339-C4

":rr c'e.-=-.cr isctopicsmix- 3

SO15 3.3359e-02lC:i 5,5737e-C2

' Isss wil l isotopics

B6-33

KCS Basis Hero 96-2DeceAer 30. 1995?iSe 32

25000 3.923Se-04end mixt

12x15 pin l a t t i c e


-kenoSSimulated shipping container exp - 4.31 wtX fuel lesd ref l (nps-5000)read pareTieterstme-2S0.0 tba-50.0 oen-120 nsk-20 npg-5000 11b-4fix-yes fdn-yes nub-yes pwt-yespit-yes run-yesend para-eters

unit 1core-" unit pin cell "cylinder 1 1 0.6324= S2.075 0.0cylinder 0 1 0.64135 92.075 0.0cylinder 2 I 0.70735 S2.075 0.0cuboid 3 1 0.946 "-0.946 0.945 -0.945 92.075 0.0

unit 2 array 1 -11.352 -15.136 0.0caii-" 12x16 pin array (assembly)"cuboid 3 1 11.35201 -11.35201 15.13601 -15.13601 92.075 0.0

unit 3com-" cr i t ical separation water gap "cuboid 3 1 11.35201 -11.35201 8.125 -8.125 92.075 0.0

global unit 4 array 2 0.O 0.0 0.0COE-" cr i t ical array geometry (3 assemblies) "'inner cuboid shell for leadcuboid 3 1 25.704 -3.0 145.148 -18.852 105.55 -17.84•outer cuboid'shell to f i l l w/leadcuboid 4 1 35.904 -13.2 145.148 -18.852 105.65 -17.84'cuboid of water tankcuboid 3 1 53.20401 -30.501 170.878 -54.122 107.275 -17.84end geometry

read arrayara-1 nux-12 nuy-16 nu2-l f i l l 192rl t end f i l lara-2 nux-1 nuy-5 nu2-l f i l l 2 3 2 3 2 t end f i l lend arrayread start nst-1 end start

read mixt sct-1' fuel isotopicsmix- 1 •

92234 5.1E43S-06-235 l.ClO-Je-03

92235 5.1403e-06238 2.'2150e-02

8016 4.5762e-02' clad isotopicsmix- 2

13027 5.8075e-0212000 5.3487e-0414000 4.6300e-0424000 1.0942e-0425055 4.4381e-0S26000 2.0374e-0429000 !.0233e-04

' moderator isotopicsmix- 3

8016 3.3369e-021001 6.6737e-02

' lead wall isotopicsmix- 4

82000 3.2771e-0229000 3.S239e-04

end mixt

setup geometry

12x16 pin latt ice

plot oecoetry

read plot

t t l " ' xy pin cell by material'nch-' o:- 'xul-0.0 xlr-1.692 yul-1.892 ylr-0.0 zul-50.0 zlr-50.0uax-1.0 vdn--1.0 nax-SO lpi-10 pic-mat end

t t l - ' xy section of 12x16 assembly by material'nch-' oo-'xui-0.0 xlr-22.704 yuI-30.272 ylr-5.0 zjl-50.0 zIr-53.0uax-1.0 vcn--1.0 nax-100 lpi-10 pic-siat end

t t l - ' xy section of cr i t ica l array by material'ncr.-' cc-*'xal-15.0 xlr-35.0 yul-!40.0 ylr--5.0 zu>53.0 zl-53.0ucx-i.o vor.--1.0 nax-100 lpi-10 pic-s:at =r,d

t t l - ' xz section of cr i t ica l array by material'nor.-' oo-*'xsl-15.0 x!r-35.0 yul-1.27 ylr-1.27 :al-50.0 z lr-10.0usx-l.O wcn--1.0 nax-100 lpi-10 pic-r,at end

d i

unit 1com-" unit pin cell "cylinder 1 1 0.63245 92.075 0.0cylinder 0 1 0.64135 92.075 0.0cylinder 2 1 0.70735 92.075 0.0cuboid 3 1 0.946 -0.946 0.946 -0.945 92.075 0.0

unit 2 array 1 -11.352 -15.136 0.0a w " 12x16 pin array (assembly)"cuboid 3 1 11.35201 -11.35201 15.13601 -15.13601 92.075 0.0

unit 3ca?-" cri t ical separation water cap "c-jboid 3 1 11.35201 -11.35201 7.175 -7.175 92.075 0.0 .

global unit 4 array 2 0.0 0.0 0.0car,-" cr i t ics) array csaretry (3 ass=7*)ie3) ""inner cuboid shell for leadcuboid 3 1 23.109 -5.405 145.143 -18.852 105.56 -17.84•outer cuboid shell to f i l l w/Hadcuboid 4 1 3S.309 -15.605 145.143 -13.852 105.55 -17.84

cui:"i ! ! 53.20*31 -30.531 173.J73 -54.122 1C7.275 -17.S4

B6-34


NCS Basis tleoo 95-2

Cscsffler 30. 1SS5

Page 33

i2x l5 pin l a t t i c e

f •"•irray

; "iux-12 nuy-16 nuz-1 f i l l 192rl t end f i l la- t'nax-1 nuy-5 nuz-1 f i l l 2 3 2 3 2 t end f i l lend arrayrsa3 start nst-1 end start

plot geometry

read plot

t t l " * xy pin cel l by material'rich-' c:- 'xy>0.0 xlr-l.SS2 yyl-1.852 ylr-0.0 2u>50.0 zlr-50.0usx-1.0 vdn—1.0 nax-80 lpi-10 pic^nat end

t t l - " xy section of 12x15 assembly by material'nch-' oo-'xul-0.0 xlr-22.704 yul-30.272 ylr-0.0 zul-50.0 zlr-50.0uax-1.0 vdn--1.0 nax-100 lpi-10 pic^nat end

t t l - ' xy section of c r i t i ca l array by material'nch-' oo-*'xul-15.0 xlr-35.0 yul-140.0 y l r - 5 . 0 zu1-5Q.O zlr-50.0uax-1.0 vdrr-1.0 nax-100 lpi-10 pic-mat end

ia l 'nch-' oo-*'xul—15.0 xlr-35.0 yul-1.27 ylr-1.27 zul-50.0 z l r -10 .0uax-1.0 wdn--1.0 nax-ICO lpi-10 piciaat endend ploten^-^atae' " ^

read geometry

unit 1CO*-" unit pin cell "cylinder 1 1 0.63245 S2.075 0.0cylinder 0 1 0.64135 92.075 0.0cylinder 2 1 0.70735 92.075 0.0cuboid 3 1 0.945 -0.945 0.S45 -0.546 92.075 0.0

unit 2 array 1 -U.352 -15.135 0.0 •car.-" 12x16 pin array (assembly)"cuboid 3 1 1!.35201 -11.25201 15.13601 -15.13501 92.075 0.0

unit 3COT.-" cr i t ica l separation water cap "cuboid 3 1 11.352 -11.352 6.485 -6.485 92.075 0.0

global unit 4 array 2 0.0 0.-0--0.0com-* cr i t ical array cecroetry (3 assemblies) "cuboid 3 1 53.20401 -30.501 147.25603 -30.503 107.275 -17.(end geometry

read arrayara-1 nux-12 nuy-16 nuz-1 f i l l 192rl t end f i l lara-2 nux-1 nuy-5 nuz-1 f i l l 2 3 2 3 2 t end f i l lend arrayread start nst-1 end start

Simulated shipping container exp - 4.31 wt? fuel water ref l(r.pg-5000)reed parametersfne-250.0 tba-60.0 gen-120 npg-5000 l ib-4fix-yes fdn-yes nub-yes pwt-yespit-yes run-yes nsk-20end parameters

plot geometry

read roixt sct-1* fuel isotopicsmix- 1

92234 5.1843e-06235 1.01We-03

92236 5.1403a-05238 2.2160e-02.

8016 4.5762e-02' clad isotopicsmix- 2

. 13027 5.8075e-C212000 5.34S7e-041^000 4.63G0e-0424003 1.0942e-0425C55 4.43Sle-0526000 ^.03745-04

isctcpics

sO:5 3.33595-021001 5.6737e-02

read plot

ttl-' xy pin cell by material"nch-' o:-'xul-0.0 xlr-1.892 yui-1.892 ylr-0.0 zul-50.0 zlr-50.0uax-1.0 vdn--i.O nex-80 lpi-10 pic-Miat end

t t l - ' xy section of 12x16 assembly by material'nch-.' oo-'xul-0.0 xlr-22.704 yul-30.272 ylr-0.0 .zul-50.0 zlr-50.0uax-1.0 vdn--1.0 nax-100 lpi-10 pic-ssat end

t t l - ' xy section of c r i t i ca l array by material'nch-' oo-'xu l -5 .0 xlr-25.0 yul-140.0 y l r - 5 . 0 zul-50.0 zlr-50.0uax-1.0 va'p."-1.0 nax-100 lpi-10 pic-mst end

t t l - ' xz section of c r i t i ca l array by material"nch-' oo-'XJI—5.0.xlr-25.0 yul-1.27 ylr-1.27 zul-100.0 zlr--10.0uax-1.0 wdn-1.0 nax-100 lpi-10 p i cke t endend plotend Cetaend

Input File for 2.35 wt* Optimum Moderated U0: Rods with Lead Reflectoret Various Distances-r.itav.-lOSS 82 2 3 4 18

1= 20 9 151SS 500 17 0 0 0

0 0 5 0 00 0

t2SS 52235 52233 13C-27 1^000 2:D55

B6-35


NCS Basis Reno S5-2De:e*>er 30. 1S55Pags 34

2=000 -25001 12000 24000

JSOOO 26000 -25001 22000

6015 1001 17000 82000

3 " 52235 253 2 0.553S 0.0697

0.0 4.E326E-04 1 15.9994 3.1135E*02

1 23S.O508 4.34S0E*02 1 1.000

9223S 293 2 0.555S O.0SS7

0.0 2.C033E-02 • 1 15.5954 7.5S36E*00

1 235.0435 2.S517E-01 1 1.000

26001 253 2 0.6350 0.0000

0.6583 2.0305E-04 1 26.58154 3.9S06£*02

1 30.4524 2.3202E»01 1 1.000

25001 253 2 0.6350 0.0000

0.5588 1.0197E-04 1 26.93154 7.S4S3E-02

1 34.0415 6.140CE-01 1 1.000 .

24300 253 2 0.6350 0.0000

J.55S3 I.MOIZ-Ot 1 25.58154 7.43C9E»02

1 35.0863 6.0!31E*0! 1 1.000

4** f2S3

t

end -kenova

2.35 w « UO2 rods wi th lead ref lector at 0.00 inread param

tTie-700 gen-120 nsk-20 npg-5000 nfb-8000

fix-yes f^n-yes pi t-yes run-yes tba-50.0nub-yes l i b -4

end param

• * HIXTU8ES

read mixt sc t -1

•fuelmix-1

92235

92238

S016

•Clad

mix-2' 33027

14000

26001

2500125055

12000

2400022000

'Water

mix-3

80161001

17000

2600082000

48000

'Leadmix-4

82000

25000

end mixt

' • GECKETSy

read cecinunit. 1

Tual

cylinder 1

cylinder 2

•a End Plu;<cylinder 2

cubcid 3LT,-.I 2 sr

UV:t 3:-br.-"Cri- Si

4.8328E-04 '

2.0033E-02

4.1043E-02

5.7S73E-022.3072E-04

2.0305E-04

1.01S7E-04

4.4230E-057.SSS1E-04

1.0504E-04

5.0725E-05

3.3427E-02

6.6S54E-02

1.00S5E-05

3.2350E-103.8505E-10

5.37S8E-11

3.2771E-021.3909E-04

•

i C.55SS 51.44 0

1 0.635 51.44 0

1 0.635 55.52 -1.27

1 1.C1S -1.015 1.016 -1.015 55.5•ray 1 -16.255 -15.304 0

global unit 4 array 2 0 0 0

'Inner sneli lea

cuboid 3 1

'Outer shell of

cuboid 4 1

'Water tank

cuboid 3 1

end ssora

32.512 O.G0 153.75 -10.25 109.33 -14.0

42.71 -10.20 153.75 -10.25 10S.33 -14.0

63.01 -30.50 174.00 -30.50 121.54 -30.5

read array

ara~l nux-15

ara-2 nux-1end array

read s tar t nst-1 end s ta r t

end iataend . -fcenova

2.35 wt% V02 roCS

read psrarri

tree-700 se.n-120 nsk-20 npg-5000 nfb-8000

fix-yes fdn-yes pit-yes run-yes tba-50.0 .

nub-yes l i b -4end param

nuy-19 nuz-1 f i l lnuy-5 nuz-1 f i l l

with les

304rl t end f i l l

2 3 2 3 2 t end f i l l

•efiector at 0,26 in

•* nisnusEs

read mixt ;

•Fuelraix-1

92235

52233

8015

'Clad

mix-213027

14000

260C1

25001

25055! 2 «

24000

22000"Water

uix-3

6016

100117000

26000

8200048000

•Leadmix-4

82000

25000end mixt

•

sct-1

4.8328E-04

2.0033E-02

4.1043E-02

5.7878E-022.3072E-04

2.0305E-04

1.01S7E-C4

4.4230E-057.9981E-04

1.0904E-04

5.0729E-05

3.3427E-02

6.68S4E-02

1.00S5E-063.2350E-10

3.S60SE-10

5.37S6E-11

3.2771E-021.350SE-04

0.5588

0.635

91.«

51.44

• * GEOMETRY •

read cecraunit 1•Fuel

cylinder 1 1•Al Clad

cylinder 2 1•Al End Flues

cylinder 2 1

cuboid 3 1unit 2 array 1

•wtit 3cc=T.-"Crit Separation"

cuboid 3 1 2f.15.256 2o5.650s'obal unit 4 array 2 0 0 0 -"inner shell lea

cuboid 3 1 33.172-0.55 153.63 -!0.37 109.33 -14.0'C-ter shel' cf

cuboid 4 1 23.37 -10.E6 153.63 -10.37 109.33 -14.0

0.635 55.52 -1.27

l.OiS -1.0:5 1.016 -1.0:5 96.62 -1.27

-16.255 -15.304 0

56.52 -1.27

B6-36


KCS Sesis Keao S5-2Oece*er 30. 1555

1 63.01 -30.50 173.76 -30.50 121.94 -30.5

r t s j arrayara-1 nux-15 nuy-19 nuz"l f i l lara-2 nux-1 • nuy-5 nuz-1 f i l ler.d arrayread,start nst-1 end startend dataend-kenova2.35 wtf U02 rods with leadread paramw.e-700 ger,-120 nsk-20 nps-5000f ix- j=s fdn-yes pit-yes run-yes tba-50.1

nub-yes Hb-4end psram

'* MIXTURES *

304rl t end f i l l2 3 2 3 2 t . end f i l l

•eflector at 1.03 i

nfb-SGOO

read mixt sct-1'Fuelmix-1

92235922388016

•Cladmix-2

1302714000250012900125055

,-7:12000

: ;'. woo•-- ;i2000'Water

niix-380161001

17000260008200048000

leadmix-4

8200025000

end mixt

•* GECKETRY

read ceon

unit 1•Fuel

cylinder 1•Al Clad

cylinder 2•Al End Plugs

cylinder 2cuboid 3

unit 2 arunit 3

4.8828E-042.0033E-024.1043E-02

5.7S78E-022.3072E-042.0305E-041.0197E-044.4230E-057.9981E-041.0904E-045.0729E-05

3.3427E-026.6854E-021.0095E-063.2350E-103.860SE-105.3795E-11

3.277IE-021.3909E-04

1 0.5583 91.44 0

1 0.635 91.44 0

1 0.635 96.62 -1.271 1.016 -1.016 1.016 -1.015 95.52

ray 1 -15.256 -19.304 '0

COT.--Crit Separation"cuboid 3

c ^ a l unit 41 2p!5.255 2S5.625 55.52 -1.27

array 2 0 0 0

read arraya r a - 3 n i i x - i S n u y l 9 nvz-1 f i l l 3 £ ) 4 r l t end f i l la.-e-2 fiux-1 nuy-5 nuz-1 f i l l 2 3 2 3 2 t end f i l lend arrayread start nst-1 end startend dataend -ksnova2.35 wtS U02 rods without lead reflectorread parastT«-700 csn-120 nsk-20 npg-SOOO nfb-8000fix-yes fdn-yes pit-yes run-yes tba-60.0nub-yes l ib -4end param

'* KDfTJRES *

read m'xt sct-1•Fuelitfx-1

92235922388016

•CUdmfx-2 •

1302714000260012900125055120002400022000

'Watermix-3

80161001

1700025000820004S000

' leadmix-4

62000• 29000

end l i i ixt

'* GEOMETRY

read geaaunit 1•Fuel

cylinder 1•Al Clad

cylinder 2'Al End Plugs

cylinder 2cuboid 3

4.8828E-04 •2.0033E-024.1043E-02

5.7878E-022.3072E-042.0305E-041.0197E-044.4230E-057.9981E-041.0904E-045.0729E-05

3.3427E-026.6854E-021.0095E-053.2350E-103.8609E-105.3798E-11

3.2771E-021.3909E-04

1 0.5588 91.44 0

1 0.635 91.44 0

1 0.635 95.52 -1.271 1.016 -1.016 1.015 -1.016 96.52 -1.27

unit 2 array 1 -16.255 -19.304 0unit 3car.-"Crit Separation"

cuboid 3global unit 4•Water «r.k

cuboid 3erd ceom

1 2P16.256 ZP4.1S5 95.6? -1.27array 2 0 0 0

1 63.01 -30.50 162.94 -30.50 121.94 -30.5

-uboii 3 1 35.123 -2.62 151.15 -32.64 109.33 -14.0'Outer shell of

cuboid 4 1 45.33 -12.S2 151.15 -12.84 105.33 -14.0'water tank

cube-id 3 1 £3.01 -30.50 153.8; -33.50 12;.r- -30.5

srs-1 nux->5 nuy-19 nuz-I f i l l 304rl t end f i l lara-2 nux-1 nuy-5 nuz-1 f i l l 2 3 2 3 2 t end f i l lend arrayread stert nst-1 end starter,i tmend

B6-37


HCS Basis Keoo 96-2December 30. 1SS5Page 36

Input File for 2.35 wtX Undermoderated UO, Rods with Lead Reflector atVarious Distances

t2SS 92235 92238 13027

29000 -29001 1200048000 26000 -260018016 1001 17000

3»* 92235 293 20.0 4.8828E-04 11 238.050! 4.3490E*02

92238 293 20.0 2.0033E-O2 11 235.0439 2.8517E-01

26001 293 20.5583 2.0306E-04 1

1 30.4624 2.3202E»0123001 293 2

0.55S3 1.0197E-04 11 34.0419 6.1400E*0!

24000 293 ' 20.5588 1.0904E-04 1

1 35.0863 6.0!31E*014 " f293t • •

end

-kencva2.35 wt! UO2 Rods P-1.684 (Undemod)read paramfse-700 gen-120 nsk-20 tba-60.0fix-yes fdn-yes nub-yes l ib-4end parani

'* MIXTURES *

14000240002200082000

0.558815.9S94

10.555815.9594

10.6350

25.961541

0.635026.98154

10.6350

25.561541

0.20533.1!35E*02

1.0000.2093

7.5S86E*001.000

0.00003.5S05E*02

0.00007.9453E*02

1.000• 0.0000

7.4309E-021.000

lead reflector e 0.00

npg-5000nfb-8000

read ir.ixt"Fuelir.ix-1

'Cladm-ix-2

92235 4.8828E-0492238 2.0033E-028016 4.1043E-02

13027 5.7878E-0214000 2.3072E-0426001 2.0305E-0429001 1.0197E-0425055 4.4230E-0512000 7.5951E-0424000 1.0904E-0422000 5.0725E-05

'Waternix-3

'Leadnix-4

8016 3.3427E-021001 6.6S54E-02

17000 8.4931E-0825000 2.5S80E-0782000 1.4532E-H48000 5.3573E-12

cylinder 1 1'A! Clad

cylinder 2 1•Al End Plugs

cylinder 2 1cuboid 3 1

unit 2 array 1ccc.-"Center Cluster"unit 3 array 2co.~-"End Cluster"unit 4ca7.-"Critical Separation

cuboid 3 1global unit 5 array 3'Inner sr.ell lead

cuboid 3 1"Outer shell of lead

cuboid 4 1"Water tank

cuboid 3 1end geoa

0.55SS

0.635

0.6354p0.642

-15.155

-15.155

- Water Gap"

91.44

91.44

95.5295.52

-19.356 .

-16.64

2pl5.156 2p5.030 96.5;0 0 0

30.312 0.00 145.11

40.51 -10.20 145.11

60.81 -30.50 156.71

0

0

-1.27-1.27-1.27

-1.27

> -1.27

-18.89 109.33 -14.08

-18.89 109.33

-30.50 127.02

-14.08

-30.50

read arrayara-1 nux-18 nuy-23 nuz-1 f i l l 414rl t end f i l lara-2 nux-18 nuy-20 nuz-1 f i l l 360rl t end f i l lara-3 nux-1 nuy-5 nuz-1end arrayend dataend*i:enov32.35 wtS U02 Rods P-l.read paraatee-700 gen-120 nsk-20'fix-yes fdn-yes nub-yesend parsm

f i l l 3 4 2 4 3 t end f i l l

(Undermod) lead reflector @ 0.25

tba-60.0 fipg-5000Hb-4 • nfo-8000

read mixt"Fuelmix-1

92235 4.8828E-0492238 2.0033E-028016 4.1043E-02

"Cladmix-2

13027 5.7878E-0214000 2.3072E-0425001 2-.0305E-0429001 1.0197E-0425055 4.4230E-0512000 7.9981E-0424000 1.0904E-0422000 5.0729E-05

'Watermix-3

8016 3.3427E-021001 6.6854E-0217000 8.4931E-0825000 2.5680E-0782000 1.4532E-U43000 5.3573M2

'Lead!7:iX"4

£2000 3.2771E-0229000 1.3509E-C4

82000 3.2771E-C225:50 1.3905E-04

"* GEOMETRY

read cex i

reed ceanur.u 1

cylinder 1 1"Ai Clad

B6-38


HCS Basis Me.ro SS-2Oeceaber 30. ISHPage 37

cylinder 2 1•Al End Plugs

- -ylindsr 2 Icuboid 3 1

ti:... 2 srrsy 1co.--"Center cluster-unit 3 array 2cCt"-"End Cluster"vr.it 4cc.Ti-"Critical Separation

cuboid 3 1global unit 5 array 3'Inner shell lead

cuboid 3 1'Outer shell of lead

c»5cid 4 1'Water tank

cuboid 3 1end gecffl

reed arrayera-1 nux*!8 nuy-23 fiuz-!ara-2 nux-18 nuy-20 nuz-:

0.635 91.44

0.635 56.524p0.842 95.52-15.156 -19.355

' -15.155 -16.84.

- Water Gap"2pl5.166 2P5.055 96.520 0 0

30.972 -0.65 145.16 -18.84 109.33

41.27 -10.85 145.15 -18.84 109.33

60.81 -30.50 155.81 -30.50 127.02

[ f i l l 414rl t end f i l l1 f i l l 360rl t end f i l l

ara-3 nux-1 nuy-5 nuz-1 - f i l l 3 4 2 4 3 t end f i l lend arrayend dataend•kenova2.35 wtX U02 Rods P-1.68'read paramUre-700 gen-120fix-yes fdn-yasend param

r,^_./nixt sct-1'FuelITiiX-l

92235 4.S523E-0492238 2.0C33E-028016 4.1043E-02

'Cladmix-2

13027 5.7873E-0214000 2.3072E-0425001 2.0305E-0425001 1.0197E-C425055 4.4230E-0512000 7.9981E-0424000 1.0904E-0422000 5.0729E-05

•Watermix-3

8015 3.3427E-021001 6.6654E-02

17000 8.4931E-C825000 2.5SE0E-C782000 1.4332E-114S000 5.3573M2

'Lead!7,ix-4

82O0O 3.2771E-02

2=vO0 1.3909E-04end Kixt

unit 1'fuel

cylinder 1 1'Al Clad

o l i ns— - 1'A! Ir.t Flu:s

0

-1.27-1.27-1.27

-1.27

-1.27

-14.08

-14.03

-30.50

1 (Undermod) lead reflector 9 1.29

nsk-20 tba-60.0 npg-5000nub-yes l ib-4 nfb-8000

0.5553 91.44 0

0


unit 2 array 1com-"Center Cluster"unit 3 array 2cc---"cnd Cluster"unit 4co.--"Critical Separation

cuboid 3 1olobal un'.t 5 array 3'Inner shell lead

• cuboid 3 1'Outer shell of lead

cuboid 4 1'Water tank

cuboid 3 1end ceom

read arrayara-1 nux-15 nuy-23 nuz-!ara-2 nux-!3 nuy-20 nuz-j

0.635 96.52 -1.274p0.842 96.52 -1.27

•15.155 -19.366 -1.27

-15.155 -16.64 -1.27

- Water 6a?"2pl5.!56 2D4.250 95.52 -1.270 0 0

33.588 -3.28 143.55 -20.45 109.33 -14.03

43.79 -13.48 143.55 -20.45 109.33 -14.08

60.81 -30.50 1S3.59 -30.53 127.02 -30.50.

I f i l l 414rl t end f i l l1 f i l l 350rl t end f i l l

are-3 nux-1 nuy-5 nuz-1 f i l l 3 4 2 4 3 t end f i l lend arrayend dataend-kencva2.35 >.« U02Rods P-!.68<read paramtie-700 cen-120fix-yes fdn-yesend paraa•**•***«******»*****

' * MIXTURES *

read mixt sct-1•Fuelmix-1

92235 4.S826E-0492238 2.0033E-02

6015 4.1043E-02•Cladmix-2

13027 -5.787SE-0214000 2.3072E-0426001 2.0305E-0429001 1.0197E-0425055 4.4230E-05120OO 7.9981E-0424300 1.0S04E-0422000 5.0729E-05

'Watermix-3

6015 3.3427E-021001 6.6854E-02

17000 8.4931E-03255D0 2.5880E-0782000 1.4532E-1145000 5.3573E-12

'Leadmix-4

82000 3.2771E-0225000 1.3905E-04

end rr,1xt

'* 6EOETCT *

m3 se^Tiunit 1•Fuel

cylinder 1 1'Al Clad

cylinder 2 1•Al i'.c Flu:3

c-.::-: 3 1

1 (t/ndermorf) without lead ref lector

nsk-20 tba-60.0 npg-5000nub-yes l i b -4 nfb-8000

0.5563 SI.44 0

0.635 ' SI.44 0

0.635 =5.52 -1.274?0.£42 95.52 -1.27

B6-39


KS Basis Ke« S5-2DecerSsr 30. 1SSS?J3e 33

unit 2 arrey 1COT-'Center Cluster"unit 3 array 2cC".""tnd Cluster"unit 4coTi»"Critical Separation

cuboid 3 1

•Water tankcuboid 3 1

er.d gean

-15.155

-15.155

' • Wster Gap"2P15.1550 0 0

60.81 -30.50 14

•19.355

•16. K

2?3.295 . S5.52

5.77 -30.50 127.02

-1.27

-1.27

-1.27

•30.50

read arrayara-1 nux-18 nuy-23 nuz-1 f i l l 414rl t end f i l lare-2 nux-18 nuy-20 nuz-1 f i l l 360rl t end f i l lara-3 n?x-l r.uy-5 nuz-1 f i 17 3 A 2 A 3 t £-:end arrayend dataend

B6-40


NCS Basis Memo 96-2December 30.1996Page 39

• Appendix B Input Files for Benchmarks used for the Statistical Analysis of the Calculations in this Basis Memo

input File for w P u Water Reflected Critical Mass as given in Table S.

OSS 82 2 3 4 IS 19 915 201SS 500 12 0 0 0 0 0 9 0 0

94239 -2390! -23902 -23903 -23904-23905 -23906 -23908 -23911-23914

1001 801623901 293 3 17.540 0.0000.0 6.146SE-5 1 1.0079 2.2161E4

1 15.9994 2.0119E3 1 1.00023902 293 3 15.700 0.000

0.0 S.3637E-5 1 1.0079 1.62S0E41 15.9994 1.4:S0E3 1 1.000

23903 293 3 ' 15.130 0.0000.0 9.7240E-5 1 1.0079 13999E4

1 15.9994 1.2708E3 1 1.00023904 .293 3 35.100 0.000

0.0 9.7492E-5 1 1.0079 1.3962E41 • 15.9994 1.2676E3 1 1.000

23905 293 3 14.370 0.0000.0 1.1966E-4 1 1.0079 1.1371E4

1 15.9994 1.0323E3 I 1.00023906 293 3 13.230 0.000

0.0 1.8390E-4 I 1.0079 7.3891E31 15.9994 6.7081E2 I 1.000

23908 293 3 12.640 0.0000.0 2.S192E-1 I 1.0079 5.3S67E3

15.9994 4.8903E223911 293 3 12.2100.0 7.4316E-4 1 1.0079

] 15.9994 1.6414E2 123914 293 . 3 8.3900.0 1.0480E-2 1 1.0079

1 15.9994 9.340100 1F293

t.0000.000

1.8080E31.000

0.0001.O28SE2

1.000

. end-kenoS

pu 24.4g/l sphere with water reflector (npg-5000)read param ime-200.0 lib-4 nsk-20 gen-120 fix-yesfdn-yes npg-5000 nub-y« tba-60.0 end paramread geometry sphere 1 1 17.54sphere 2 1 48.02cuboid 0 1 6P48.0S

readmi t mix-1 23901 6.1468-5 80163.3387-2 1001 6.6774-2mix-2 8016 3.3455S-2 1001 6.69116-2 s e f l end mixtend data end

Inpur File for "*Pu with a Thin Ste<S.-nitawl

1 Shell and Full Water Reflection at given in Table

2SS 8016 7014 100124000 28000 26000 -2600194238 9-239 94240 94241 94242

3 " 94239 299.8 3 17.7800 0.00000.0 6.6QWE-05 I 1.0079 2.OO92E-O4

1 15.8772 2.0505E-03 ' 1 1.00026001 299.8 3 17.9070 0.000

0.0 0.061S 1 5S.69 2.3121 51.9960 1.15-J6E-00 1 1.0M

ktr,o5 •J BENCHMARK 4 SPHERE WITH STEEL SHELL AND WATER REFLECTOR

(np£»5000) read param tme-200.0 lib-4 r.sk-20 gen-120 fix-yesfdn-yes nub-yes r.pg»5000 tba-60.0 end paramread gcomeirv sphere 1 1 17.78Sphere 2 1 17.907sphere 3 1 46.000

cuboid 0 1 6P46.IO0endeeomread mixt mix-1 9-1239 6.6004-5 9 4 2 « 3.5692-77014 7.5114-4 S016 3.4514-2 1001 6.5006-2 2S0OO 1.5457-6mix-2 26001 6.1TSE-2 24000 1.658-2 280OO 8.15S-3mix-3 8016 3.332-2 1001 6.663-2 SCt-I end mixt

id data

with a Thin Steel Shell and No Wat.

80162J0O094238

94239

70142S0OO94239

299.80.0 S.2232E-O5

1001 26000 -26001

94240 94241 94242• 3 19.3130 0.0000

1 1.0079 1.6254E+O41 15.8987 I.6340E-O3 1 1.000

94240 299.8 3 19.3180 0.00000.03.9321E-06 1 1.0079 3.3992E+05

1 16.0003 3.4396E-4M 1 1.00026001 299.8 3 19.4400 0.00000.0 6.3310E-02 1 58.69 1.7995ET<H)

1 51.9960 1.1234E-KW 1 1.0004 " 1299.8

end-kenaiPU BENXHMARK 4 SPHERE ^TTH STEEL REFLECTOR (npg-5000)read param tme-200.0 lib-4 nsk-20 gen-120 fix-yesfdn-yes npj-5000 nub-yes tba-60.0 end paramrcadgeomeay sphere 1 1 19.318sphere 2 119 .«cuboid 016P19.5end geomread mint roix-1 94239 8^232-5 94240 3 . 9 J 2 1 - 6 94241 2.6356-794242 5.3567-9 7014 6.4132-4 8016 3.4536-2 1001 6.5520-2 26000 6.965*7mix"2 26001 6.331E-2 24000 1.654-2 28000 6.51-3 sct-1 end mixtend data end

!S 8016 7014 1001 24000 2SOO094238 94239 94240 94241 9434226000 -26001 -26002 12000 1302720000 19000 25055 14000 11023

' • 94239 296 3 17.8700 0.00000.0 8.506OE-O5 1 1.0079 1.4673E*O4

1 15.7040 1.8144E+03 1 1.00094240 296 3 17.8700 0.0000

0.04.0700E-06 1- j.0079 3.0665E+051 15.794J 3.8144ETO4 1 1.000

26001 296 3 17.9820 0.00000.0 6J310E-02 1 58.69 1.7995E-O0

1 51.9960 I.I23JE-00 1 1.000 •26002 296 3.0000E-KW 28.142 0.0000

0.0 0.0013 1 1.0079 264.W51 18.0027 1.6293E-KQ 1 1-000

25055 296 3.0000E-00 2S.142 0.00000.0 2.756OE-O5 1 1.0079 12857.329

i JS.S550 S . 4 S : : E - 0 3 I 1.00011023 296 3.0QOOE-00 ZS.142 0.0000O.Ol.NiOE-04 1 1.0079 3094.742

1 1S.SI23 2.040SE-03 I 1.000•f296

B6-41


NCS Basis Memo 96-2December 30,1996Paje 40

(5000)read param tme-200.0 lib—1 nsk-20 gcn-120 fix-yesfdn-yes npg-SOOO nub-yes tba-60.0 end paramreadfeomeay sphere 1 1 17.S7sphere 2 1 17.9S2sphere 3 1 23.142cuboid 0 I 6P2S.2

•PU 1S0T0PICSmix-1 94239 S.506-5 94240 4.070-6 9424! 2.7-794243 6.0-9 7014 2.098-340!6 3.601-2 1001 6.118-2 26000 7.3-7•STEEL VESSEL ISOTOPICSmix=2 26001 6.331E-2 24000 1.654-2 28000 6.51-3'CONCRETE ISOTOPICSmix-3 12000 7.62-4 13O27 3.353-3 20OOO2.6O9-3 26OO2I.342-319000 4.35S-4 25055 2.756-5 14000 1.293-2 1001 1.737-211023 1.145-1 8016 4.529-2 SCl-1 end irend data

Input File fc-nitawlOSS 82

end

°'Pu with * 4" Concrete Shell i s given in Table 5.

8016260001900028000

94239

7014-2600125055

2980.0 7.SS28E-05

1001 94239 9424012000 13027 2000014000 11023 24000

3 17.7800 0.0000 '1 1.0079 1.6419E-W

1 15.8238 I . 7 9 7 5 E T 4 3 1 1.00094240 298 3 17.7S00 0.0000

0.0 3.7S51E-O6 I 1.0079 3.4195E+0S1 15.9157 3.7659E+04 • 1 t.000

26000 298 3 17.89176 0.00000.0 6.3310E-O2 1 58.69 1.799

1 51.9960 1.1234E-'OO 1 1.00026001' 298 3 28.05176 0.0000

0.0 1.3417E-03 1 1.0079 2.6444E-HJ21 17.6042 1.5657E+02 - 1 1.000

25055 298 3 28.05176 0.00000.0 2.7673E-05 1 1.0079 1.2821E-KJ4

I 18.4810 8.1422E+03 1 1.00011023 298 3 28.05176 0.00000.0 1.1417E-O4 I 1.0079 3.1O77E+O3

1 18.4778 1.9708E+03 1 1.0004 " f298

end-keoo5PU SPHERE WITH STEEL SHELL AND 4" CONCRETE REFLECTOR (npg-5000)read param tme-200.0 lib—4 nsk-20 iba-60.0 gen-120 fU-yesfdn-yes pit-yes nub-yes mn-yes npi^5000 end parararead geometry sphere I I 17.7Ssphere 2 1 17.8918sphere 3 1 28.05cuboid 0 1 6P2S.1endgcomread mixt

•PU ISOTOPICSmix-1 94239 7.833-594240 3.785-67014 1.146-38016 3.516-2100! 6.345-2

•STEEL VESSEL ISOTOPICSmijc-2 26000 6.331E-224000 1.654-22SO0O 6.51-3•CONCRETE ISOTOPiCS

12000 7.619-413027 3353-3200002.609-326001 1.342-319000 4.357-425055 2.767-51-000 1.293-2

1001 1.739-211023 1.142-18016 4.53-2

read plotCil-'XY SECTION THROUGH CENTER OF SPHERE"nch-'O-'1

xuI-45.0 x!r-45.0 yul-45.0 ylr—15.0 zuI-0.0 zJr-0.0uax-1.0 vdi-1 .0 nax-SO.O lpi-10.0 pic-mai end plotend data end

Input File for *"Puw a 10"Con te Shell »•

2SS 8016 7014 1001 94239 9424026000 -26001 12000 13027 2000019000 25055 14000 11023 2S00O24000

3 " 94239 298 3 17.7800 0.00000.0 7.1137E-O5 1 1.0079 1.7945E+O41 15.8213 1.9691E-O3 1 1.000

94240 298 3 17.7SOO"" 0.00000.0 3.41SSE-06 1 1.0079 3.7373E-K151 15.9052 4.1233E+O4 1 1.000

26000 298 3 17.89176 0.00000.0 6.331OE-O2 1 58.69 1.7995E-KK)1 51.9960 1.1234E+00 1 1.000

26001 29E 3 43.29176 0.00000.0 U417E-03 1 1.0079 2.6444E+021 17.6042 1.5657E*O2 1 1.000

250JS 298 3 43.29176 0.00000.0 2.7673E-05 1 1.0079 1.2821E+O41 18.4810 8.1422E*O3 1 J.000

11023 298 3 4329176 0.00000.0 1.M17E-04 1 1.0079 3.1077E+O31 18.4778 1.970SE+03 I 1.000

4 " f29Stend-keno5PU SPHERE WITH STEEL SHELL AND 10" CONCRETE REFLECTOR (npg-5000)lead param tme<00.0 !ib*4 nsls-20 tba-60.0 gen-120 flx-yesfdo-j'es p!i-yes nub-yes run-yes npg-5000 end paramread geometry sphere 1 1 17.78sphere 21 17.8918sphere 3 1 43.29cuboid 01 6P44.0end geom

TUISOTOP3CSmix-I 94239 7.114-594240 3.416-67014 1.146-38016 3.473-23001 6.25S-2•STEEL VESSEL ISOTOPICSmix-2 26000 6331E-2240001.654-228000 6.51-3•CONCRETE ISOTOPiCSmix-312000 7.619-J13027 3.353-3200002.609-326001 1.342-3190004J57-J25055 2.76%514000 3.293-21001 1.739-211023 U42-48016 4.53-2sc;-l end mixttead plotnl-'XY SECTION' THROUGH CENTER OF SPHERE1

wh- 'O-"xu'.—45.0 xIr-45.0 vul-i5.0 ylr—45.0 zul-0.0 zlr-0.0uax'I.O v*s»-1.0 RW-80.0 lpi-10.0 pic-ma! end plot

B6-42



922547014

2200016000

92236601211023

92238S01612000

.pui File for a 4x4 Concrete Reflected Array of 93.2 wt% Enriched Uranyl Nitrate ato7.:S f/I at given in Tabie 5.-nitawlOSS S2 2 3 4 IS

19 20 9 15 " •ISS 500 17 0 0 0

0 0 6 0 00 0

I2SS 92235

26000 7014 6012 8016 10012000019000

3 " 92234 293 2 10.5600 0.95020.0 1.7693E-06 1 1.0079 7.5125E-051 16.1609 7.4984E-KW I 1.000

92235 293 2 10.5600 0.95020.0 1.6061E-04 1 1.0079 S.2758E+031 15.9415 E.1445E-02 1 1.000

92236 293 2 10.5600 0.95020.0 7.4495E-07 1 1.0079 1.7843E4O61 16.1622 1.7811E-KJ5 1 1.000

92238 293 2 10.5600 0.95020.0 9.1432E-06 1 1.0079 1.4537E-K151 16.1517 I.4502E-I-04 1 1.000

26000 293 1 25.4000 0.00000.0 2.527SE-O4 1 1.0079 8.3939E+021 16.7297 8.9763E-tO2 1 1.000

11023 293 1 25.4000 0.00000.0 3.8303E-04 1 1.0079 5.5395E--021 16.8578 S.9671E+02 1 1.000

4 " f293

end"kenova

_^_ROT53 4x4 array of UN solution w/o sleeve (67.28 gU/1-21.12 crs~ ""^adparam gen-120 nsk*2O npg-5000 nfb-8000\ ._: ^e-700 fdn=y« pl 'Tes run-yes iba-60.0'*—'Ilx-yes lib—4 nub-yes

92234922359223692238

1.7693E-O61.6061E-047.4495E-079.U32E-O6

8016 3.41J9E-O27014 4.I162E-041001 6.S156E-O2

mix«2'Altank

13027mix-3•Concrete

12000130272000026000

. 1900014000

S.9469E-02

7.18S5E-041.1241E-038.0213E-032.527EE-O44.8976E-047.7139E-O3

1001 1.0401E-0211023 3.S303E-04

8016 4.2362E-026012 6.42J7E-03TOM I.995SE-0S

160002:000

er.d mixi

S.2S0SE-052.9I92E-05

:o.T.--Sph«e U255 «--Ji gU-Wt.12 eicylinder 1 1 0.505 0.00 -0.32cylinder 2 1 10.56 0.00 -0..-2

cylinder 1 1cylinder 0 1cylinder 2 1cuboid 0 1

evlinder 1cylinder 2

cuboid 3

cvlinder 1

111

1cylinder 2 1

cuboid 0unit 4

cylinder 1cvlinder 2cylinder I

1

111

10.5610.5610.96

27.15119.1119.1

15.24 -15.24

0.5050.635

-0.32-0J2-0.32

15.24 -15.24 123.445-0.32

25.40 0.0025.40 0.00

15.24 -15.24

0.5050.635

5.005.00

15.24 -15.24.

1.1410.5610.56

0.000.0027.15

15.24 -15.24 25.4 0.0

0.000.00

15.24 -15.24 5.0 0.0

•0.32-032-0.32

- ..... . . 10.S6 I19.I -0.52cylinder: 1 10.96 119.1 -0.32

cuboid 0 1 15.24-15.24 15.34-15.24 123.445-0.32it 5

cylinder! 1 1.U0 25.40 0.00cylinder 2 1 1.270 25.40 0.00cuboid 3 1 15.24 -15.24 15.24 -15.24 25.4 0.0


cuboid 0 1unit 7 array-! 0.0 0.0 0.0unit 8 «rey»2 0.0 0.0 0.0unit 9 amv-3 0.00.00.0unit 1<

1.140 5.00 0.001270 5.00 0.00

15.24 -15.24 15.24 --15:24 5.0 0.0

cuboid 0 1 121.92 0.0 0.14 0.0121.92 0.0 0.14 0.0cuboid 3 1

cuboid 0 1uni t l l

cuboid 0 1

lit 12cuboid 0cuboid 5 1.cuboid 0 1cuboid 3 1

4 0.0

25.7 0.0 122.2 0.025.7 0.0 122.2 0.025.7 0.0 122.2 0.025.7 0!0 122.2 0.0

0.0

unit 14global ur

175.32 0.0 25.7 0.0173.32 0.0 25.7 0.0173.32 0.0 25.7 0.0

y-4 0.0 0.0 0.0arrav-5 0.0 0.0 0,0

15 array-6 0.00.0 0.00 1 0.0 0.0 0.0 0.03 1 0.0 0.0 0.0 0.0

5.0 0.030.4 0.0154.165 0.0

5.0 0.030.4 0.031.035 0.0154.165 0.0

5.0 0.030.4 0.031.035 0.0154.165 0.0

0.635 0.01.025.4 0.0 1.0

ara-1 oiara-2 DIix- 3 nuv-lara-3 nux~4 cuy-4

ara-4 mara-5 mar3=6 niend arrayread plotttl-'Plot'xul=0 xli

7 8 7 77 8 7 77 7 7 7

JX-1 nuv-3JX-3 na\--lixrl nu\--3

nuz-3 fillnui-3 fillnuz-1 fill

end fillmiz-1 fillnuz-1 fillnuz-1 fill

r-125 >-u!-71.46 ylr-7uax-1 wdn«-l nax-

tni da: a

3 2 1 end fill6 5 4 end fill7 7 7 7

10910 eadfill11 13 11 end fill12 14 12 end fill

1.46 zu l -166dr -S130ndn-S0 lpi«10 pie-mix end

a 2\l Concrete Reflected Array of 93.2 wt% Enriched Uranyl Xnr,ver, in Table 5.

OSS E2 2 3 4 IS19 20 9 15

ISS SQO I? O 0 O0 0 6 Q 00 0

2SS 9221-5 S;;:-4 <

B6-43


KCS Basis Memo 96-2December 30,1996Paje 42

26000 7014 6012 SOI 6" 100120000 22000 11023 12000 1302719000 16000

3 " 92234 293 2 10.5600 0.95020.0 2.00O9E-O6 1 1.0079 6.6236E-*«5I 16.1S16 6.687CE-Q4 I (.000

92235 293 2 10.5600 0.95020.0 l.S16iE-04 1 1.0079 7.2963E->031 15.9552 7.250-E-02 1 1.000

92236 293 2 10.5600 0.95020.0 8.42J0E-07 1 1.0079 1.S731E-O6I 16.1829 1.SBS3E-1-05 1 1.000

922J8 293 2 10.5600 0.9S020.0 1.034IE-05 1 1.0079 I.2S16E+051 16.1712 1.2930E-04 I 1.000

26000 293 I 25.400 0.00000.0 2.527SE-04 1 1.0079 8.3939E-021 16.7297 S.9763E-02 1 1.000

11023 293 1 25.400 0.00000.0 3.S303E-04 ) 1.0079 5.S3WE-HJ21 16.8578 5.9671E+O2 1 1.000

4 " f293

-kenova• ROT54 2x2 array Wo sleeve (76.09 gtM-21.12 cm diamcyl)

read param £en*I20 nsk»20 np$-5000 nfb-8000mie-700 fdn-yes plfyes nin-yes tba-60.0fix-yes lib-4 nub=yesend paramread mix!

•• MIXTURES •

Tuel92234922359223692233801670141001

mix-2•Altank

13027mix-3'Concrete

120001302720000260001900014000100111023

• 8016601270141600022000

end mixt

2.0OO9E-O61.SI64E-048.4250E-071.0341E-O5

3.424SE-024.7215E-O46.4966E-O2

S.9469E-02

7.1S85E-O41.1241E-03S.0213E-O32.527SE-O44.8976E-O47.7139E-031.0401E-023.63<J3E-Q<t4.23S2E-026.4237E-O31.9958E-0S82S09E-052.9192E-0S

'* GEOMETRY •

ead geominii 1

cylinder I 1cylinder 2 1cylinder 1 Jcylinder 0 1cylinder 2 1

0.505 0.00 -0.3210.56 0.00 -0.3210,56 62.34 -0.3210.56 119.1 -0.3210.96 119.1 -0.32

cubcidO 1 15.24 -15.24 15.24 -15.24 123.44J-0.32

0.505 25.40 0.000.635 25.40 0.00

15.24 -15.24 15.24 -15.24 25.4 0.0

0.505 5.00 0,00 .0.635 5.00 0.00

15.24 -15.2-1 15.24 -15.24 5.0 0.0

cylinder I I 1.14 0.00 -0.32cylinder 2 I 10.56 0.00 -0.32cylinder 1 1 10.56 62.34 -0.32cylindirO 1 10.56 119.1 -0.32cylinder 2 1 10.96 119.1 -0.32cuboid0 1 15.24 -15.24 15.24 -1J.24 123.44J-0.3;

unit 5cylinder 1 I 1.140 25.40 0.00cylinder^ 1 1.270 25.40 0.00

unit 6cylinder I 1 1.140 J.00 0.00cy!inder2 J j.27-0 S.00 0.00

cuboid 0 1 15.24 -15.24 15.24 -15.24 5.0 0.0unit 7 array-1 0.0 0.0 0.0unit 8 array-2 0.0 0.0 0.0unit 9 array-3 o.O 0.0 0.0unit 10

cuboid 0 1 30.48 0.0 60.96 0.0 5.0 0.0cuboid 3 J 30.48 0.0 60.96 0.0 30.4 0.0cuboid 0 1 30.48 0.0 60.96 0.0 154.165 0.0

unit 11cuboidO 1 121.92 0.0 30.62 O.O 5.0 0.0cuboid3 1 121.92 0.0 30.620.0 30.4 0.0cuboidO 1 17.1.92 0.0 30.620.0 154.1650.0

unit 12cuboidO 1 25.7 0.0 122.2 0.0""5.0 0.0euboid3 1 25.7 0.0 122.2 0.0 30.4 0.0cuboidO 1 25.7 0.0 122.2 0.0 51.03SO.Ocuboid 3 1 25.7 0.0 122.2 0.0 154.165 0.0

unit 13cuboidO I 173.32 0.0 25.7 0.0 5.0 0.0cuboid 3 1 173.32 0.0 25.7 0.0 30.4 0.0cuboidO 1 173.32 0.0 25.7 0.0 31.035 0.0cuboid 3 1 173.32 0.0 25.7 0.0 154.165 0.0

unit 14 airay-4 0.0 0.0 0.0unit 15 array-5 0.0 0.0 0.0unit 16 arraywti O.O 0.0 0.0 'global unit 17 arrsy-7 0.0 0.0 0.0reflector 0 1 ' 0.0 0.0 0.0 0.0 0.635 0.0 1.0reflector 3,1 0.00.0 0.0 0.0 25.4 0.01.0end geam

- ARRAY '

n- lnuy- l nu2-3 fill 32 1 end fillc-1 nuy-1 rmz-3 fill 6 5 4 end fill

a/s-4 nux-3ara-5 nux-lara-6 nux-3ara-7 nux-1end arraylead plotnl-TJot* ncxul-25. xlr-7uax-1 wdn»-end plotend data

noy»l nuz-1 fillnu>-«3 nur-1 fill

nu>-»3 nui-lfill

h-' •;.' pfc-mix

S 7 8 7109101114 11215 113161

3yu!-71.46 ylr-71.461 nax-130 ndn-SO lp|-

1213

Za10

endfitfend fillend fillend fillend (it!

1-166 zlr-1end

Jnpat File for a 4x4 Concrete Refiectfd Amy o!93.t » t t Enriched Vnnv) fiitr.360.37 gfl as givtn in T«ble 5.

OSS 82 2 3 4 IS19 20 9 15

1SS 500 23 0 0 00 0 10 o 00 0

:SS 92235 9 ; ; M 92236 9223S 1400026000 CSOOt 6012 8016 100120000 2:OC>0 11023 12000 1302719000 16303 15031 25055 420007014 2-&00 2SO0O

3 " 92234 293 2 83800 0:65760.0 9.4767E-C6 1 1.0079 1.2499E-KIS1 16.702] 1.8007EHJ4 1 1.000

92235 293 3 S.3S0O 0.65760.0 S.50r£-C4 1 1.0079 1.3769E-03 '! 15.75S- 1 S5TSE-C2 1 1.000

B6-44

NCS Basis Memo 9S-2December 30.1996Page 43


92236 293 2 8.3S0O 0.65760.0 3.9902E-O6 I 1.0079 2.968iE+051 16.7073 4.2781E-O4 1 1.000

92238 293 2 8.3S0O 0.65760.0 4.8974E-05 1 1.0079 2.4185E-041 16.6623 3.4759E-03 1 1.000

26000 293 I 25.4000 0.00000.0 2.S27SE-O4 1 1.0079 8.3939E-^O21 16.7297 S.9763E---02 1 1.000

11023 293 1 25.4000 0.00000.0 3.S303E-04 1 1.0079 5.539SE-O21 16.8578 S.9671E-rO2 1 1.000

26001 293 1 0.3100 . 0.00000.0 S.9852E-02 1 58.69 2.2046E-00I 48.1197 4.0995E-02 ! 1.000

25055 293 1 0.3100 0.00000.0 1.1209E-03 1 55.847 6.0S72E-021 S4.21S0 3.6440E-02 1 1.000

24000 293 1 0.3100 0.00000.0 1.6985E-02 1 55.847 4.O171E-O11 55.4800 3.562IE-02 1 1.000

28000 293 I 0.3100 0.00000.0 7.5400E-03 1 55.847 9.0492E+O11 4S.U97 4.0995E-02 1 1.000

" f293

ROT61 4x4 array UN solution w/sleeve (360.37 eU/l-16.1 2 eireadparam een-120 nsk-20 npg-5000 nfb-8000

70 run-yes lba»60.0une-700fix-yesendparamread mixt

fdn-yes p1

] i b -4 ' nub<

•• MIXTURES •

mix-1• \iel

•; 92234922359223692238

9.4767E-068.6027E-043.9902E-O64.8974E-05

SO 16 3.7295E-O27014 2.1I977E-03

13027 5.9469E-02

Si«l Sleeve260012400028000

5.9852E-021.6985E-027.5400E-03

6012 2.6231E-04140001503116000

• 2S05542000

mix-4

120001302720000260001900014000

1.376SE-033.S530E-052.8282E-O5I.1209E-03S.9563E-06

7.18SSE-041.1241E-03S.0213E-032.J278E-044.S976E-047.7139E-03

1001 1.0-J01E-0211023 3.8303E-04

S016 4.2-62E-O26012 6.4:TC1-J 1.9:

16000iJsE-05

S.2S09E-052.919;-E-O5

•GEOMETRY •

c>i:sJsrli i o.5o; ooo -o..-;

cylinder 2 1 8.06 0.00 -0.32cylinder! I 8.06 3232 -0.32cylinderO 1 8.06 119.1 -0.32cylinder2 1 8.38 119.1 -0.32

cylinders 1

cvlinderl 1cylinder 2 1

3cylinder! 1cylinder 2 1

4eviiader) icylinder 2 1cylinder 1 1cylinder 0 1cylinder 2 1evIindtrO 1cvtinder3 1

cuboid 0 1

cylinder 1 1cvlinder2 1

cuboid 4 1

cylinder! 1cylinder 2 Icuboid 0 1

8.69

0.5050.635

121.68 -0.32

25.40 0.0025.40 0.00 '

0.50S 5.000.635

. I.i48.06S.06S.OS8.388.388.69

5.00

0.000.0032.32119.1119.1

0.000.00

-0.32•0.32-0J2-0.32-0J2

121.68 -0.32121.68 -0.32

15.24 -15.24

1.1401.270

15.24 -15.24 123.445-0.32

25.40 0.0025.40 0.00

15.24 -15.24

1.1401.270

5.005.00

15.24 -15.24

15.24 -15.24 25.4 0.0

0.000.00

15.24 -15.24 5.0 0.0unit 7 a.Tay-1 0.0 0.0 0.0iinitS arra>-2 0.0 0.0 0.0wit 9 array-3 0.0 0.0 0.0

cuboid 0 Icuboid 4 Icuboid 0 I

unit IIcuboid 0 1cuboid 4 Icuboid 0 1cuboid 4 1

unit 12cuboid 0 1cuboid 4 1cuboid 0 1cuboid 4 1

unit 1 j i i ay -

121.92 0.0121.92 0.0121.92 0.0

0.14' 0.00.14 0.00.14 0.0

25.7 0.0 122.20.025.7 0.0. 1222 0.025.7 0.0 122.2 0.025.7 0.0 122.2 0.0

25.7 0.025.7 0.025.7 O.O25.7 0.0

173.32 0.0173.32 0.0173.32 0.0173.32 0.0

I 0.0 0.0 0.0yS 0.0 0.0 0.0

global unit 15 a m y - 6 0.0 0.0 0.0reflector 0 1 . 0.0 0.0 0.0 0.0reflector 4 1 0.0 0.0 0.0 0.0

'• ARRAY •

5.0 0.030.4 0.0154.165 0.0

5.0 0.030.4 0.0

31.035 0.0154.16J 0.0

5.0 0.030.4 0.0

31.035 0.0154.165 0.0

ara-2 nuara-3 nu

:x-1 nuy-1ix-1 nuy-1;x-J nuy-4 •

7 8 7 7

nuz-3 fsllnuz-3 fillnuz-1 fill

7 7 7 7 end fillara-4 nuara-5 nuar»-6 nuend arrayread plotnl-Tlot'

uax»! wderd pldend data

x-1 nuy-3:x»3 nuy-1•x-I nuv-3

neh"' *!.'

rs"-l "nsx"'

nuz-t fillnuz-1 fillnuz-1 fill

picmix

3 2 16 5 4

end fillend fill

7 7 7 7

10911 131214

1.46 vlr-71.46130 nd-TSOIpi-

10 endfiil11 end fill12 end fill

zul-166z!r-3• 10. end

Input File for 4.31 wtV. Enriched UndermoderateiJ t O , Fuel Rods with a Lead WailReflector i s ;ivcn in Table 5.

B6-45

tiCS Basis Memo 96-2December 30,1996


92238290001600012000

293

13027-2900124O0017000

2

820OO26000

' 2000022000

0.632S

8016•26001

6012O.lSOl

2SS 92235• 1 0 0 1

1400025055

3 " 922350.0 1.0124E-03 1 15.9994 1.69S0E*O2

1 238.0508 2.3237E-02 1 1.00092238 293 2 0.6325 0.1801

0.0 2.2193E-02 1 15.9994 7.74i9EfOO1 255.0439 5J372E-01 1 1.000

26001 2S3 2 0.6985 0.00000.6325 2.O3OSE-W 1 26.98154 3.9906E+02

I 30.4624 2J202E-01 f 1.00029001 293 2 0.698S 0.0000

0.6325 I.O197E-04 J 2$.98iS4 /.94«H*02I 34.M19 6.1400E-4J1 ] 1.000

24000 293 2 0.6985 0.00000.6325 1.0904E-04 1 26.98154 7.4309E-02

1 35.0S63 6.0131E-01 1 1.0004 " f293

end

4.31 wi% U02rods withlead refiectorai 0.00inread paramime-700 gen-120 nsk-20 lib-4 npg-SOOOfix-yes fdn-yes iba-60.0 nub-yes nfb-8000end param

'• MIXTURES •

lead mixt7uelmix-1

92235922388016

'Clad .mix-2

1302714000260012900125055120002400022000

•Water

801610011700026000

•Leadmix--)

8200029000

SCl-1

1.0124E-O32.2193E-O2

4.6411E-02

5.7878E-022.3072E-042.O305E-O41.0197E-044.4230E-057.9981 E-04I.09WE-046.1944E-OS

3.3427E-O26.685SE-028.4931E-082.58S0E-07

3.2771E-021.B909E-04

•Rubber End Caps

60121001

2000014000801616000

end mixt

3.S41SE-02S.1304E-022.2627E-034.21 S3 E-041.0989E-028.4975E-05

'• GEOMETRY '

cylinder 1cvlinder 3cyiinder 2cylinder 5

e-jboid 3t 2 J.T3V

0.632450.641350.70735'0.70735

91.4491.4491.4493.98

000

-2.50.946 -0.946 0.946-0.946'93.9S

-15.136 •11.552 0

com--Crit Separation"cuboid3 1 1J.136-15.1368.870-S.870 93.98 -2.54

global unit 4 srcay 2 0 0 0"Inner shell for lead

cuboid3 1 30.2720.00 145.15-18.85 109.96-13.44•Outer shell to fill w.iead

cuboid 4 1 40.47-10.20 145.15-18.85 109.96-13.44•Water tank

cuboid3 I 60.77-30.50 156.80-30,50121.94-30.50endgeom

read array«]6nuy»12 nuz-1 fill 192M t end fill-1 nu j -5 ntu-1 fill 2 3 2 3 21 end fill

4.51 HIM VO2 rods with Uadread param

fix-yes fdn-yes tba-60.0end param

lib>*4 npg-5000nub-yes nfb-8000

•• MIXTURES •

readmixt•Fuel

9223592238£016

•Cladmix-2

13027(4000260012900125055120002400022000

'Waterroix-3

£016100117000260O0

•Lead

8200029000

sct-1

1.O124E-O32.2193E-O24.6411E-02

5.7S7SE-O22.-072E-O42.0305E-O41.0197E-O44.4330E-0S7.9981 E-041.09O4E-O46.1944E-05

3J427E-O26.6SS5E-O28.4931E-O82.5SS0E-O7

3.2771E-O21.3909E-04

•Rubber End Caps

60121001

2000014000301616000

enrfmi'xt

3.8415E-O25.1304E-022.2627E-O34.2I83E-M1.09S9E-02S.4975E-0S

'• GEOMETRY •

cylinder 1 1cylinder 3 1c>'Jind«2 I1

cylinder 5 1"euboidS 1

it 2 array 1it 3m-"CriI S:par;

cuboid 5 1

0.632450.641350.507550.70735

91.44 091.44 09J;44 095.98 -2.54

0.946-0.946 0.946-0.946 93.98 -2.5-15.136

ition"

•11.352 0

15.136-15.136 9.090-9.090 93.98 -2global unit 4 array 2 0 0 0'Inner shell for lead

cuboidS 1 30.932-0.66 K5.59-1S.41 109.96-13.44•Outer shell to fill w/lead

cubo:d4 1 40.47-10.20 145.59-18.41109.96-13.44•Water i n k

caboid 5 1 60.77-30.50 15/.65-30.50 121.94-30.50

B6-46


NCS Basis Memo 96-2December 30,1996Pane 45

end a.Tavend data'end*kenova4.31 wt%read paramtme-700fix-yes 1end param

UO2 rods with lead

jen-120 nsk-20fdn-yes tba-60.0 i

•• MIXTURES •


92235922388016.

•Clad

1302714000260012900125055120002400022000

•Watermix-3

8016100117000

\ 26000lead

fnix-48200029000

SCl-l

1.0124E-032.2I93E-O24.6411E-O2

5.787SE-022.3072E-042.0305E-O41.0I97E-044.423OE-O5 '7.9981E-041.0904E-046.1944E-05

3.3427E-O26.6855E-028.4931 E-OS2.5SS0E-O7

3.2771E-021.3909E-O4

•Rubber End Capsmix-J

60121001

2000014000E01616000

3.S415E-02'S.I304E-022.2627E-034.21S3E-041.0989E-028.4975E-0S

•* GEOMETRY *

read jeom

cylinder 1cylinder 3cylinder 2cylinder 5

1 0.632451 0.641351 0.707351 0.70735

reflecio:

lib-4nub-yes

91.4491.4491.4493.98

I t end fill

r at 0.77 in

npg-5000nfb-SOOO

000

-2.54cuboid 3 1 0.946 -0.946 6.946 -0.946 93.98 -2.54

unit 2 am;>• 1 -15.136 •31352 0

eom-'Crit Separation"euboid3 1 15.136-15.1368.715-8.715 93.98 -2.54

global uni!4 array 2 0 0 0'Inner shell for lead

cuboid3 1 32.228-1.96 144.S4 -19.36 109.96-13.44Ouwr shell to fill w,1ead

ccboid4 1 40.47-10.20 144.84-19.16 109.96-13.44

e-jbv.it 1 60.77-30.50 156.18-30.50 121.94-30.50

4.31 «1% UO2rod:

tme-700" gen-120 nsk-20 lib-4fix-yes fdn-yes tba-60.0 nub-ye

" MIXTURES'

:ad reileciorat 1.97 in

92235922388016

•Clad

1302714000260012900125055120002400022000

•Watermix-3

801610011700026000

'Lead

. 8200029000

1.0I24E-032.2193E-O24.6411E-02

5.TSTSE-022.3O72E-O42.03O5E-O41.0I97E-044.4230E-057.998 IE-041.09O4E-O46.I94JE-05

3.3427E-O26.6S55E-028.4931 E-OS2.5S80E-07

3.2771E-021.59O9E-04

'Rubber End Caps

60121001

' 2000014000801616000

3.841SE-025.1304E-022.2627E-034J1S3E-O41.09S9E-028.4975E-05

cylinder 1cvlinder3cvlinder2cvlindir5

cuboid 3on it 2 array

1

1111

0.632450.641350.707350.70735

0.946 -0.946•15.136

91.4491.4491.4493.98

000

-2.540.946 -0.946 93.98 -2.54

-11.352 0

com--Crit SeparatJon-euboidS 1 15.136-15.136 7.175-7.175 93.98 -2.54

global unit 4 axray2 0 0 0"Inner shell for lead

cuboid3 1 35^73-5.00 141.76-22.24 109.96-13.44'Outer shell to fill w/lcad

cuboid4 1 40.47-10.20 141.76-22.24 109.96-13.44'Water 12.1k

euboid3 1 60.77-30.50 150.O2-3O.5O121.94-30.5O

read a n y

wiihoui lead reriecio:

»l iiuy-5

tT.e-700 £tr.-120 rsk-20fix-v-es fii«i-es iba-60.0 nub-yes

B6-47



92235 1.0124E-O39223S 2.2193E-O28016 4.64ME-02

13027 5.7S7SE-O2MOW 2.3G72E-0426001 2.0305E-0429001 1.0197E-O425055 4.4230E-0S12000 7.9981E-0424000 1.0904E-Q422O00 6.I944E-05

"Waier

S016 3.3427E-021001 6.68S5E-02

17000 8.4931E-08260O0 2.58SOE-O7

'Leadmix-4

82000 3.2771E-0229000 1.3909E-04

'Rubber End Capsmix-S

6012 3.S-II5E-021001 S.13WE-02

20000 2.2627E-0314000 4.2183E-O48016 1.09S9E-0216000 S.4975E-O5

•• GEOMETRY •

read geomunit 1

cylinder 1 1cylinder 3 1cylinder 2 1cylinder5 1cuboidS 1

0.63245 91.44 00.64135 91.44 00.70735 91.44 00.70735 93.98 -2.54

0.946 -0.946 0.946 -0.946 93.98 -2.54•15.136 -11.352 0

*"Crit Separation"cuboid3 1 15.136-15.1366.4S5-6.48S 93.98 -2.S4

globalunii4 array2 0 0 0•Waiertajik

cuboid 3 1 60.77-30.50 147.26-3O.J0 121.94-30.50end gei

read array

1 30.4624 2.3202£J-01 1 1.00029001 293 2 0.70735 0.0000

0.64J35 1.019TE-04 1 26.98154 7.9463E-O2'1 -4.0419 6.I400E-r01 1 1.000

24000 293 2 0.70735 0.00000.64135 1.0904E-04 1 26.98154 7.4309E-O2

1 35.OS63 6.013IE-01 1 1.0004 " O93tend

4.31 «1% UO2 rods P-2.S4 cm (Opt Mod) lead reflector @ 0.00 inreadparamtme-700 gen-120 nsk-20 lib-4 npg-5000fix-yes fdn-yes tba-60.0 nub-yes nfb-SOOO.runwes end paiam

•• MIXTURES •

9223592238E016

1.0124E-O32.219-E-O24.64HE-02

1302714000260012900125055120002400022000

5.7S7SE-02JJ072E-O12.0305E-041.0197E-044.4230E-05

.99SIE-041.0904E-04J.0729E-05

, -16nuj-12x«l nuy-5

z-lfill 192rlt eudfill- lf i! l 2 3 2 3 21 endfiil

1001 6.68J6E-O217000 5.129SE-O726000 3.23 50E-1082000 1.4532E-1148000 3.2144E-U7014 4.0792E-09

- S20O0 3.2771E-0229000 1.3909E-04

"Rubber End Caps

6012 3.S415E-021001 5.1304E-02

20000 2.2627E-03160O04.21S3E-0480161.09S9E-0214000 8.4975E-05

Input File for 431 wl"/. Enriched Ontimum Moderated L'O] Fuel RodReflector i s given in Table 5.

with a Lead Walt

OSS S219

1SS S0000

2SS 92235100114000250554SOO0

3 " 92235

220

21O0

9223B290001600012000

2930.0 1.0124E-03

1 239223S

3 49 IS

0 05 0 0

IS

0

13027 S2000 SOIt-29001 26000

24000 2000017000 22030

2 0.63251 15.9994

S.0508 2.3237E-02 1393 2 0.6325

-2600170146012

0.04091.69SC€-02

1.0000.0409

0.0 2.2193E-02 1 15.9994 7.745SE-001 235.0439 5.33T2E-01 1 1.000

26001 293 2 0.70Ti< O.00M0.W135 2.O3C5E-04 1 ;5.?£iJ4 :-.990S£-0

read geomunit 1com-"Single Fuel Pin*

cylindcrl I 0.63245cylinder 0 1 0.64135cylinder 2 1 0.70735cylinder 5 1 0.70735

cuboid 3 1

91.44 091.44 091.44 ' 093.93 -2.54

1.27O-1.27OI.27O-1.27O 93.98 -2.54unit 2 a-Tayl -10.16 -16.51 -2.54cosi*"13 x E 2.Tay of pins*

com-"Critical S=pi.-a;ion - Water Gap-cuboid 3 1 2pl0.160 2pl0.310 93.98 -2.J4

global uni: - array 2 0 0 0•L-.n!rsh*!] for lead

cuboidS 1 20.3200.00 152.1S-ll.SS 107.42-15.9S•Oy::r shi!! to fill wish lead

cuboid 4 1 30.52 -10.20 152.15 -11.S5 107.42 -15.98•Waseruofc

cuboid 3 1 50.82 -30.50 170.80 -30.50 121.94 -30.50

B6-48


NCS Basis Memo 96-2December 30.1996Pane 47

lilt )04rl t end fillHI! 2 3 2 3 21 end fill

kenova.31 wi% UO2 rods P-2.S-I cm (Opt Mod) leadreflecior @ 0.26 inead param.3 U

read param0

read paramane«7O0 gen-120 nsk-20 lib—4 npg-5000flx»y« fdn"yes tba»60.0 nub»yes nfb"8OOOrun™ycs end paism

end dataend

4.31 will UO2 rods P-2.J4 cm (Opt Mod) lead reflector @ 0.52 in

tme-700 gen-120 r.sk-20 lib-4 npg-5000fl\"\'es fdr.'^'es tba~60.0 nub-jes nfb-8Q00run-yes end param

•• MIXTURES *

92235 1.012iE-0392238 2.2I93E-02S016 4.641 IE-02

13027 5.78TSE-0214000 2.3072E-0426001 2.0305E-0429001 1.0197E-0425055 4.4230E-05I2OO07.99S1E-0424000 1.0904E-0422000 J.0729E-O5

"Watermix-3

8016 3.342SE-021001 6.6856E-02I7000 5.129SE-0726000 3.23S0E-10820001.4532E-1I

> 4S000 3.2144E-H'j/ 7014 4.0792E-09

mix-482000 3.2771E-0229000 U909E-04

•Rubber End Caps-mix-5

6012 3.84I5E-021001 5.1304E-02

20000 2.2627E-O316000 4.21S3E-O4£016 1.09S9E-0214000 8.497JE-O5

end mixt

unit 1 'eora--Sine]e Fuel Pin-

cylinder I 1 0.63245 91.44 0e>!inderO 1 0.64135 91.44 0cylinder 2 1 0.707SS 91.44 0cylinders 1 0.70735 93.98 -2.54cvboidl } • 1.270-1.270 1.270-1.270 95.9$ -2.54 .

unit 2 array 1 -10.16 -16.51 -2.54com-"I5 x 8 array of pins"unit 3com-"Criiical Separation - Water Gap"

cuboid 3 I 2p30.160 2pl0J90 93.98 -2.54globs] unit 4 array 2 0 0 0

cuboid i ]• 20.980 -0.66 152.31 -11.69 107.42 -15.98•Ov.it shdl to O m\h lead

cuboid 4 I 3I.1S-10.S6 152.31 -11.69 107.42-I5.9S•Wate: tank

cuboid 5 1 50.S2-30.50 171.12-30.50 321.94-30.50end j t o n

read array3,-a-l nus"Smiy-13m:z-] fill 10-Srl t endfiili-a-2 nux-i n-jy-s nuz-\ f:ll 2 3 2 3 2 t end fillendair^y

92235 1.0IJ4E-039223S2.2593E-O280164.W11E-02

13027 S.7S78E-O2UQ002.S012E-Q426001 2.0305E-O429O011.0I&7E-O425055 4.4330E-O512000 7.998IE-0424000 1.09O4E-O422CM5O 5-0729E-O5

1001 6.6S56E-0217000 5.139SE-0726000 5.255OE-1OS2000 1.45S2E-1148000 3.2H4E-117014 4.0792E-O9

82000 3.2771E-O229000 1J909E-O4

'Rubber End Caps

60123.84IJE-O21001 J.lJOiE-02

20000 2.2627E-03I60004.2ISJE-O48016I.0989E-0214000 S.4975E-05

•• GEOMETRY •

readjeora

com--SiB£le Fuel Pin"cylinder 1 1 0.63245 91.44 0eytindeiO I 0.64(35 91.4* 0cylinder^ 1 0.70735 91.44 0cylinder 5 1 0.70735 93.98 -2.54cuboid3 1 U 7 0 - U 7 0 1 . 2 7 0 - t . 2 7 0 93.98-2.54

unit 2 array! -10.16 -16.51 -2.54eom»"13 x£ array of pins'

eom-'Criiieal Separation - Water Gap"cuboidS 1 2pl0.!60 2p9.520 93.98 -2.54

global unit4 artsy 2 0 0 0liner shell for lead

euboidS 1 21.641-1.32 150.57-13.43 107.42-15.98•Outer shell to fit! with lead

cuboid i 1 31.84-11.52 150.57-13.43 107.42-13.9S

cuboid 3 I 50.82 -30.50 167.61 -30.50 121.94 -30.50

ara"! nux-i

end anayend (Js;a

IJZ-l12-1

fill IWrl t efill 2 3 2 3 2

no fill[ end fill

4.31 «-,% UO! rods P-2.54 cm <Opl Mod) icad reflector ig 2.13

B6-49


NCS Basis Memo 96-2December 30.1996Page 48

jen-120 nsk-20fdn-yes tba-60.0

endparam

lib-4 npg-5000nub-yes n(b-SOOO

92235 J.O12JE-O3922382.2193E-028016 4.6411E-02

13027 5.78TSE-0214000 2.3072E-0426001 2.0305E-0429001 1.019TE-0425055 4.4230E-O512000 7.9981E-0424000 1.0904E-0422000 S.0729E-0J

S0I6 3.3428E-O21001 6.6856E-02

17000 5.129SE-O726000 3.2350E-I082000 1.4532E-1148000 3.2144E-I1701-1 4.0792E-09

S2OOO3.277IE-O229000 I.3909E-04

•Rubber End Capsmix-5

6012 3.8415E-021001 S.1304E-02

20000 2.2627E-03160004.21S3E-048016 1.09S9E-0214000 S.-1975E-05

'• GEOMETRY •

read jeomunit 1eom-'Single Fuel Pin"

cylinder 1 1 0.63245 91.44 0cylinder 0 1 0.64135 91.44 0cylinder 2 1 0.70735 91.44 0cylinder 5 I 0.70735 93.98 -2.54

cuboid 3 1 U70-1.270 1.270-1.270 93.98-2.54unii2 sway! -10.16 -16.51 -2.54com-"13 x 8 array of pins"unit 3com-'Critical Separation - Water Gap"

cuboid 3 1 2pl0.160 2p5.150 93.98-2.54global unii4 array 2 0 0 0'Inner shell for lead

cuboidS 1 25.725-5.41 141.83-22.17 107.42-15.98"Ouier shell to fill with lead

cuboid4 1 35.93-15.61 141.83-22.17 107.42-15.98'Water tank

cuboid 3 1 50.82 -30.50 150.16 -30.50 121.94 -30.50

S nuy"13 ni:i=l fill 104rl I end fill\ nuy-S nu : - l fill 2 3 2 3 21 end fill

-kenovaJ.31 vn*,i UO2 tods P-2.54 cm (Op! Mod) wshow lead reflectorread para.-nIms-TOO j;en-120 nsk-30 . l:b-4 np™5000f.x-l'es fdti »yes tbs"60.0 nub^'es r.fb-SOOO

92235 1-0J24E-039223S 2.2195E-O2E016 4.64HE-02

13027 5.7S78E-O214000 2.3072E-0426001 2.03QSE-O429001 1.0197E-O425055 4.4230E-0512000 7.99S1E-04240O0 1.09WE-0422000 5.0729E-OS

8016 3.342SE-021O016.6856E-02

17OOO5.I2S3E-O726000 3.235OE-1O82000 1.4J32E-1148000 3.2144E-1I7014 4.0793E-O9 •

82000 3.2771E-02- 29000 U905E-O4

•Rubber End Caps

6012 3.8415E-O21001 5.1304E-02

2OOO0 2.2627E-O316000 4.21S3E-O480161.09S9E-0214000 8.-J97JE-05

unit 1com-"Single Fuel Pin1

cylinder 1 Icylinder 0 1cylinder 2 1

l i d s 1y

cyli

0.632450.641350.707350.70735

91.4491.4493.98

-uboidS 1 1J270-U70U70-1.270 93.98 -2.54unit2 array I -10.16 -16.51 -2.54com--13x8arrayofpins-unit 3eom--CriticalSeparation -WaterGap-

cuboid 3 1 2pl0.160 2p4.120 93.98 -2.54global unit 4 array 2 0 0 0•Water tank

cuboid 3 1 50.82 -30.50 146.04 -30.50 121.94 -30.J0end geom

read 3,-rayara-1 nux-S nuy>13 n u i - 1 " fill )04rl t end fillara»2 nux-1 nuy-S nuz-1 fill 2 3 2 3 21 end fill

Input File for 2.35 wtV. Enriched Undermoderated L'O, Fuel Rods wiltReflector as given in Table 5.

OSS 82 ' 2 3 4 IS19 20 9 15

1SS 500 17 .0 0 0

2SS 92235 92238 13027 1400029000 -25001 12000 24000iSOOO 2600D -26001 22000£016 1001 17000 S2000

B6-50


92235 293 2 O.55S8 0.20980.04.SS2SE-04 1 15.999-1 3.1135E-02

1 23S.OS08 4.3490E-rO2 1 1.00092238

0.0 2.O033E-021 235.0459 2.!

26001 2930.55SS 2.030SE-O4

1 30.4624 2.3202E-0129001 293 2 0.6350

0.5588 0.20981 15.9994 7.5SS6E-O0

7E-01 I 1.0002 0.6350 0.0000

1 26.98154 3.9906E-021.000

0.00000.55S8 1.0197E-04 1 26.98154 7.9J63E-K12

1 34.0419 6.1400E-KJ1 1 1.00024000 293 2 0.6350 0.0000

O.5J8S 1.0904E-04 1 26.98154 7.430SE-021 35.0863 6.0131E-0I 1 1.000

4 " f293

end

2.35 w;% U 0 2 Rods P-1.684 (Undermod) lead reflecior @ 0.lead paramtme-700 gen-120 nsk-20 lba«60.0 npe-5000 'flx-yei fdn-yes nub-yes lib-4 nffc-3000endparam

'• MIXTURES •

readm'Fuel

92235 4.S828E-0492238 2.OO33E-O280164.1043E-02

•Clad

13027 S.7S7SE-0214000 2.3072E-O4

, 260012.030SE-04•:• i 29001'1.0197E-O4• 'J 25055 4.4230E-0S

" ' 12000 7.9981E-O424000 1.Q904E-O422000 5.O729E-O5

•Watermix-3

S016.3.3427E-021001 6.6854E-02

17000 8.493IE-0826000 2.5880E-O782000 1.4S32E-1148000 5.3573E-12

•Lead

82O0O3.2771E-O229000 1.3909E-04

end mixt

'• GEOMETRY •

unil ITuel

cylinder 1 1•Al Clad

cylinder 2 !•Al End Plufs


unil 2 array 1eom-'Cemer Cluster"unh 3 array 2 -15.156

O.55SS

0.63S

0.6354p0.842-15.156

96.5296.52

-19.366

cuboid 3 1 30.512 0.00 145.11-18.89109.33-14.08•Oussr shell of lead

cuboid 4 I 40.51 -10.20 145.11 -18.89 109.3- -14.08•W2T=n=:;k

r^bc:d3 I 6 0 S ! -50.50 !56.71 -30.50 12/.C:-30.50

read i i a yara-1 nux-18 nu;-23 nm-1 fill 414rl t end fill

fill 36Orl t end fillfill 3 4 2 4 3tend fill

2.35 v.1%UO2 Rods P-l.684 (Undemiod) lead (edecior@ 0.26d

ilx-yesendpara

nsk-20nub-jes

92235 4.8S28E-O492238 2.O033E-O28016 4.1045E-O2

13027 5.787SE-0214000 2.3072E-0426001 2.03OJE-O429001 1.0197E-0425055 4.4230E-0512000 7.99S1E-O4240O0 1.0904E-0422000 5.O729E-OS

S016 3J427E^I21001 6.6S54E-02

17000 8.4931E-08.26000 2.5SSOE-O782000 1.4532E-M48000 5J573E-12

•Lead

" GEOMETRY •

read gtom

Tuclcylinder! 1

•Al Clade>'linder2 1

•Al End Plugscylinder 2 1

cuboid 3 1

com-'Ceater Cluster*

0.5588

O.63S

0.6354p0.842-15.156

91.44

91.44 •

96.52

96.52-19.366

--End'ciusier-•15.156- -16.84

com-"Critical Separation - Water Gap"' cuboid3 1 2pl5.)56 • 2p5.055 96.52-1.27jlobai unii 5 array 3 0 0 0'Inner shell lead. cuboid 3 1 30.972 -0.66 145.16 -18.84 109.33 -14.08•Ouser shell of lead

cuboid 4 1 41.17-10.86 145.16-18.84 109.33-14.08•\Va:

er.duboid 3 1 60.S1 -30.S0 156.81 -30.50 127.02 -30.50

d array- l S nuy-23 n

ara-2nux-3Snuy-:O nars«3 niw-1 nu\-5

-1 fill 414il t end fill- 1 fill 560rlt end fillr -1 fill 3 4 2 4 3 t end fill

B6-51


NCS Basis Memo 96-2December 30,1996Page JO

•kenova2.35 wt% UO2 Rods P-1.684 (Undermod) lead renector @read parwntme-700 ^en-120 nsk-20 tba-60.0 npg-5000fix-yes fdn-yes nub-yes lib-4end param

•• MIXTURES *

readmixl scl-1"Fuelmix-1

92235 4.S82SE-O492238 2.OO33E-O2S016 4.1O45E-O2

'Cladmix-2

15027 S.787SE-O214000 23O72E-0426001 2.0305E-O429001 1.0197E-04250S5 4.4230E-0S120OO7.99S1E-O424000 1.0904E-W22000 5.0729E-05

•Watermix-3

80I6 3.3427E-021001 6.6S54E-02

17000 8.4931E-0826OO0 2.5S30E-0782000 1.4532E-1148000 5.3573E-12

leadmix-4

82000 3.2771E-0229000 1.3909E-04

end mixl

- GEOMETRY •

-r™Hinder 1 1 0.5588

•Al Cladcylinder 2 1 0.635

'Al End Plugscv!inder2 1 0.635

cuboid 3 ) 4pO.S42unit2arrav| -15.156com«-Cemer Cluster"unit3arra>-2 -15.156com-"End Cluster"

91.44

91.44

96.52• 96.52

-19.366

•16.84

0

0

-1.27-1.27-1.27

•1.27

com-"Critical Separation - Water Gap"cuboid 3 I 2plJ.156 2p4.3S0 96.52-1.27

global unit 5 array 3 0 0 0'Inner shell lead

euboid3 I 33.588 -3.28 143.55 -20.45 109.33 -14.08•Outer shell of lead

euboid 4 1 43.79 -13.48 143.55 -20.45 109.33 -14.08•Water tank

cuboid 3 1 60.81 -30.50 153.59 -30.50 127.02 -30.50end geom

ead a.-ray

•teaova2.55 w.% UOread pararatme-700flx-j-es fdend pa.-am

fill 414rl tend fillf)l) MQrl t end fflfill 3 4 2 4 3 1 end :T

s P-1.6S1 (L-ndsrmoti) wiL

92255 4.SS2SE-049223S 2.O033E-028016 4.10C-E-02

adx-2

l-O27J.-;s:gE-O214000 2.-Q72E4426001 2.O3O5E-O429001 1.0197E-0425055 4.4230E-O512000 7.9981E-0424000 1.0904 E-0422000 5.O729E-O5

8016 y-127E-O21001 6.68S4E-0217000 8.493 IE-OS26000 2.5ES0E-07S2D0O1.4532E-I14SOOO5.3575E-12

82000 3.2771E-0229000 1.5909E-04

read geom •

'Fuelcylinder 1 1 0.558S 91.44 0

VU Cladcylinder 2 1 0.635 91.44 0

*AI End Plugscylinde.-2 1 0.635 96.52 -1.27

euboid 3 1 4p0.842 96.52 -1.27unit 2 array 1 -15.156 -19.366 -1.27com--Center Clustet'uni: Sarray2 -15.156 -16.84 -1.27eom»"End Ouster"

com""Cridcal Separation • Water Gap"euboid3 1 2pl5.1J6 2p3.295 96.52-1.27

global unit 5 array 3 0 0 0"Water tank

cuboid 3 1 60.81 -30.50 149.77 -30.50 127.02 -30.50

read arrayara-1 nux-18 nuy-23 nuz-1 fill 414rl t end fillara-2 nux-18 nuj-20 nuz-1 fill 360rI t end filla ja-3nux-l mi'y-j suz-1 fill 3 4 2 4 31 end fillend arrayend dataend

Input FtJe for 135 wi% Enriched Optimum .Moderated UO, Fuel Rods with i Lead WallReflector is j i n n in Table 5. .

I 92255 92238 13027 14000 2505529000 .29S0I 12000 240004SO00 26000 -26001 22000SDi6 1001 17000 S200O« : ? 5 295 2 O.558S 0.0897

0.0 4.is:SE-04- 1 15.9994 3.1I3SE-02 .1 25S.0508 4.349OE-02 1 1.000

92238 -2S3 2 0.5588 0.0S970.0 2.O035E-02 1 li.9994 7.5SS6E-001 "\£04."9 2.SII/E-01 I 1.000

26CC1 293 2 0.63J0 0.0000O.f-!ES :,0-0;E-04 1 26.9S154 3.99D6E-02

B6-52

NCS Basis Memo 96-2December 30.1996Page SI


1 30.4624 2.3202E-OI 1 1.00029001 193 2 0.6350 0.0000O.55SS 1.0197E-04 1 26.9E154 7.9463E-02

1 34.0419 6.140CE-OI 1 1.00024000 393 2 0.6350 0.00000.S5SS 1.0904E-04 1 26.9S154 T.450SE-02

1 35.OSS3 6.0131E-OI 1 1.0004 " f293

end-kenova2.35 «i% UO2 rods with lead reflector at 0.00 inread paramime-700 gen-120 nsk-20 npg-5000 nfb-8000fix-yes fdn"yes pk-yes run»yes tba-60.0nub-yes lib-4

- MIXTURES p

read mixt•Fuel

9223592238SOI 6

•Clad

1302714000260012900125055120002400022000

•Watermix-3\ 8016

' 10011700026000$200048000

leadmix-4

S200029000

end mit t '

SC!-1

4.8S2SE-042.OO33E-O2

•J.1045E-02

S.787SE-O22.3072E-042.0305E-041.0197E-04J.423OE-O57.9981 E-041.0904E-045.0729E-05

3.3427E-026.6S54E-O21.0O95E-0532550E-103.S609E-105.3798E-1I

3.2771E-O21.3909E-04

"• GEOMETRY •

tttd jeorn

"Fuelcylinder 1 1 0.5SSS 91.44 0

•A! Cladcylinder 2 1 0.635 91.-14 0

'Al End Plugscylinder' I 0.635 96.S2 -1.27

cuboid3 I 1.016-1.016 1.0)6-J 01696.52 -1.27unit 2 array 1 -16.256 -19.304 0unit 3comH Cnt oepafaEion

cuboids 1 2pl6.256 2p6.920 96.52 -1.27global unit 4 array 2 0 0 0Inner shell tea

cuboid 5 ) 32.5J20.00 )53."5 -J0.2S 109.:-:- -)i,0'Outer shell of

cuboid 4 1 42.71-10.20 153.75 .10 25 109.33 -14.0•Waitrtar.1;

c-jboid3 1 63.01 -50.50 174.OO.j0.5O 121.94-30.5end geom

rcai!«ny

.•a-2 nux-1 nay-5 nui-'l fill 2 & 2 3 2 t end fiilend anaylead s;a.T ns:»l end s:anend data

2.35 WT% UO2 rods with lead reflector at 0.26 inread paia.-ntme-700 £«n>*120 nik-20 npg-5000 rJb»SOfk-yes fdn-\es plr->'es run*jes iba-60.0nub«yes lib^lend pi'i-ti

92235 4.SS28E-O492238 2.M33E-02£016 4.1043E-02

JJ027 5.?S7S£-O214000 2.3072E-0426001 2.0305E-0429001 1.0197E-0425055 4.4230E-0512000 7.998 tE-0424000 1.0904E-M22000 S.0729E-OS

S0I6 3.3427E-O21001 6.6E54E-0217000 1.O095E-O626000 323J0E-IO82000 3.86O9E-1O48000 5.3798E-11

82000 3^771E-0229000 1.3909E-04

endmixt

unit!•Fuel

cylinder] 1. 0.5588 91.44 • 0•Al Clad

cylinder 2 1. 0.635 91.44 0•Al End Plugs

cylinder 2 1 0.635 96,52 -1.27cuboidj 1 1.016-1.016 1.016-1.01696.52 -1.27

unit 2 array 1 -16.256 -19.304 0unit 3com-"Crit Separation*

cuboid 3 1 2pl6.256 2p6.860 96.52 -1.27global unit 4 array2 0 0 0•Inner shell lea

cuboid 3 1 33.172-0.66 153.63-10.37 109.33-14.0•Outer sbell of

cuboid 4 1 43.37-10.86 153.63-10.37 109.33-14.0•Water tank

euboid3 1 63.01-30.50 173.76-30.50 121.94-30.Send geom

-16 nuy-19 nuz-1 fill 30-Srl t end fill- l nu>-5 nuz-1 fill 2 3 2 3 21 end fill

end array

end dataend-fcenova2.35 wfii

read pa.-a.iitme-TOO

n^b-^'esend p'aram

-

L-02 rods «-i:h lead

gsn-120 nsk-20faa«\-es plt-^-es nl;b-4

• MLXTVRSS'

read nixt sc:»l

reflecior a

npg-5000

t 1.03 in

ntV-SODba-60.0

B6-53


NCS Basis Mlemo 96-2December 30,1996Page 52

mix-19223592238SOI 6

•dad

1302714000-260012900125055120002400022000

'Water

80161001

17000260008200048000

Leadmix-4

8200029000

4.SS2SE-042.OO33E-03-J.10J3E-02

S.787SE-022.3072E-O42.0305E-041.0197E-044.4230E-0S7.99S1E-041.0904E-04S.O729E-O5

3.3427E-026.68S4E-021.009IE-063.23S0E-103.86O9E-105.3798E-11

3.2771E-021.3909E-04

0.5588

0.635

91.44

91,44

- GEOMETRY •

•Fuelcylinder] 1

'AlCIad

cylinder 2 1'A! End Plugs

cylinder 2 1cuboids 1

unit 2 array 1

unit 3com-'Crit Separation"

cuboid 3 I 2pl6.256 2pS.625 96.52-1.27global unit4 array 2 0 0 0'Inner shell lea

35.12S -2.62 151.16 -12.84 109.33 -14.0

- 0.635 96.52 - U 71.016-1.016 1.016-1.016*6.52 -1.27

-16.256 -19.304 0

cuboid 3 1•Outer Shell of

cuboid 4 1"Water lank

cuboid 3 1end geom

read array

45.33 -12.82 151.16 -12.84 109.33 -14.0

63.01 -30.50 168.82 -30.50121.94 -30.5

end arrayread stanend data

nuy"I9 nu i " l fill 3Wrl t end fillnuy-5 nui -1 fill 2 3 2 3 2 1 end fill

120002400022000

'Wiser

S0161001!70O026000820OO48000

•Lsadmix-4

8200029000

7.9981 E-041.0904E-045.0729E-O5

3.3J27E-026.6S54E-021.0095E-063.235OE-1O3.S6O9E-1O5.379SE-11

3.2771E-02I.3909E-04

read jeomunit 1•Fuel

cylinder I 1'Al Clad

cylinder 2 1'Al End Plugs

cvlinder2 1cuboid 3 1

unit 2 arrav I

O.55SS

0.635

0.63S1.016-1.016

-16.256

91:44

91.44

96.52'1.016-1-19J0.

O

0

•"•• - 1 . 2 7

.016 96.52 -1.27i o

com-"Crit Separation'cuboid 3 1 2pl6.256 2p4.1J5 96.52 -1XI

global unit 4 array 2 0 0 0

endgeom

read array

63.01 -30.50 162.94-30.50121.94-30.5

nuy-19 nuz-lfi l l 304rl t end fillnuy-5 nuz>imi 2 3 2 3 2 1 end fill

read paramtme-700

fd

UO2 rods

•120• - . ' «

lib-4rublesend param

'• MIXTURES •

readmixt sct-1 .'Fuel

92235 4.SS:$E-0492238 2.M33E-02S016 4.iC4:-E-02

rsk-20 npg-5000 nfb-SOOOpit-yes • run-j'es tba»60.0

13027 5.7S7SE-O2i-iooo 2.;O::E-O426001 2.O305E-O429001 1.0197E-W25055 4 . J :5C-E-05

B6-54


7.0 STRUCTURAL EVALUATION

7.1 INTRODUCTION

The PRTR Graphite Cask, or Radiometallurgy Cask 27, is an onsite, intra-area packaging fortransporting Type B radioactive material within the 300 Area of the Hanford Site. This section of thedocument defines and evaluates the NTC structural requirements for intra-area transport of thispackage. Structural performance of the package is evaluated only for NTC; accident conditions areevaluated in the risk and dose consequence section of this document.

7.2 STRUCTURAL EVALUATION OF PACKAGE

7.2.1 Package Structural Description

The PRTR Graphite Cask is fundamentally a right circular cylinder of lead and stainless steelcomposite construction. The lead is sandwiched between outer and inner stainless steel tubular shells.At each end of the cask is a thick circular plate, that is welded to both inner and outer shells, whichencapsulates the lead. At the top, closure of the inner cavity is provided by a bolted blind flange withan attached shield plug of composite lead-stainless steel construction. The cask is equipped with amanually actuated, rotating, shielded drum door, which provides closure at the bottom end. None ofthe end closures are sealed. A handling yoke is provided on the cask and welded to the outer shell.Attached to the yoke is a lifting bail, which can be locked into position for lifting and handling of thecask. Support plates are welded to the outer bottom housing to provide support during transport.

The cask is constructed of welded 304 stainless steel. Shielding is provided by lead, which ispoured after fabrication of the stainless steel body and internal components.

7.2.2 Chemical and Galvanic Reactions

At the operating temperatures, no chemical or galvanic interaction of the materials will occur.The lead is encapsulated in the stainless steel; consequently, there are no agents to generate chemicalor galvanic reactions, (n addition, stainless steel forms a natural oxide layer, which provides protectionfrom most corrosive agents (i.e., water) under the normal operating temperatures.

7.2.3 Sizes of Package and Cavity

The outside dimensions of the cask are 36.0 cm (14.0 in.) in diameter by 99.0 cm (39.0 in.) inlength. Dimensions of the inner cavity are 7.94 cm { 3.13 in.) in diameter by 63.5 cm (25.0 in.) inlength.

7.2.4 Weight

The PRTR Graphite Cask has an empty weight of 1,089 kg (2,400 Ib) and a maximum grossweight of 1,202 kg (2,650 Ib).

7.2.5 Tamper- Indicating Devices

Due to the weight of the cask closures and the intra-area shipment of this cask, no tamperindicating devices are provided.

B7-1


7.2.6 Positive Closure

Positive closure of the cask is provided by the bolted blind end flanges. The top end blindflange is secured with four, No. 10 hex head screws. At the bottom end the flange is closed off with arotating shielded drum door.

7.2.7 Lifting and Tiedown Devices

No tiedown devices are provided on the cask. For lifting and handling, yokes on each side ofthe cask with a rotating bail are provided. The yokes are recessed into the outer housing andreinforced with welded plates. The bail is equipped with bearings that are pressed onto the yoke. Asshown in the Part B, Section 7.5, the yoke and the lifting attachments meet the requirements of theHanford Site Hoisting and Rigging Manual (RL1993).



Onsite structural performance of the package is assessed for Hanford Site normal conditions inthis section. The onsite conditions evaluated for are hot and cold temperature extremes, reduced andincreased external pressure, vibration, water spray, compression, inertial loading, and penetration. Thepackage structural response with solar insolation is evaluated for the onsite hot ambient temperatureextreme of 46 °C (115 °F [Fadeff 1992]} and without for the cold, ambient temperature extreme of-33 °C (-27 °F [Fadeff 1992]). Reduced and increased external pressure structural response isevaluated for a Hanford Site maximum barometric pressure range of 0.94 atm (13.81 psi} to 1.01 atm(14.85 psi). Vibrational loading response of the package is evaluated for the parameters established inANSI N14.23 (ANSI 1980). In the case of water spray, package response is evaluated for in-leakage ofwater at ambient temperatures and pressures. The package structural response to compression isevaluated for compressive loads resulting from anticipated stacking onto the package. Because thereare no in-transient load transfers, structural response of the package to inertial loads is evaluated forrough transport of the package based on ANSI N14.23 shock loading parameters. Penetrationstructural response is idealized as a loading from a steel rod 3.2 cm (1.25 in.) in diameter with arounded end weighing 6.0 kg (13.0 Ib) dropping onto the package from a height of 1.0 m (40.0 in.).These loads are to be applied independently and nonsequentially.


The criteria for acceptable performance of the package are based on all major criticalcomponents of the package remaining structurally functional, the contents remaining contained, andonly superficial damage of noncritical components being incurred during NTC. To meet the criteria forNTC, the analytical tests are to assume, as a worst case, the package is intermittently subjected to theabove loading conditions during normal transport operations. Performances of the package in meetingthese criteria are demonstrated by either positive margins of safety based on material yield strength orpackage loadings that are within acceptable limits of the component/materials used in the package.

7.3.3 Hot and Cold Evaluation

Based on the thermal evaluation from Part B, Section 8.0, for a worst-case heat source of5.65 W with solar insolation under Hanford Site conditions, the maximum internal componenttemperature of the cask is 79 °C (175 °F). Considering the materials of construction (lead andstainless steel), no material degradation or appreciable reduction in yield strength will occur. Under

B7-2


these conditions the external temperature of the cask is 78 °C (172 °F). Consequently, structuralperformance of the package is not affected by the Hanford Site hot temperature extreme. Followingthe thermal analysis, the radiological payload activity was reduced, resulting in a heat loading of2.92 W. Because the heat loading is less than that previously analyzed, the conclusions remain thesame.

Evaluation of cold temperature package performance shows that because the primary structuralmaterial of construction is stainless steel, no extremely cold weather shipping restrictions are required.Austenitic stainless steel is not susceptible to low-temperature brittle fracture. Consequently, with anonsite, low, extremely cold temperature of -33 °C (-27 °F), no degradation cask of performance willoccur.

7.3.4 Reduced and Increased External Pressure

Because the cask is not sealed, reduced or increased external pressure is not a concern.

7.3.5 Vibration

Vibration of the package is not a concern because the shipment occurs only 12 times a year fora distance of less than 1.61 km (1.0 mi). Based on a speed of 24 km/h (15 mi/h) for a distance of1.61 km (1.0 mi), 12 times a year, at a loading frequency of 2 Hz (ANSI 1980), this equates toapproximately 6,000 cycles per year. Relative to the loading on the materials and the material fatiguestrengths, vibrational loading on this cask is not significant.

7.3.6 Water Spray

Because the package is not sealed, in-leakage of water into the cask cavity is a concern.Consequently, all payloads must be shipped in sealed containers. Prior to and after transport, the caskmust be inspected for any in-leakage of water into the cask cavity.

7.3.7 Compression

The package is shipped as an exclusive-use shipment, and stacking on the package isprohibited. Consequently, package compression is not a concern.

7.3.8 Inertial Loading

During normal transport of this package, no in-transit load transfers are involved.Consequently, normal condition inertial loads would arise from rough transport shock loads of 3.55svertical to the plane of travel and 2.3£rs in the direction of travel (ANSI 1980).

In the case of the rough transport, shock loads of the conveyance are evaluated as intermittentin nature and applied as a single pulse to the package. Because the duration of the shock load is ofsuch long duration (greater than three times the natural frequency of the system), it is applied as aquasi-static load, and the package is evaluated by classical linear elastic methods. To ensurecomponent and material loading are within the elastic range, the allowable stresses are established onthe basis of the maximum shear stress theory of failure. The weld allowable loading is established onbase material yield strength with a joint efficiency reduction factor based on the American Society ofMechanical Engineers Boiler and Pressure Vessel Code, Section VIII (ASME 1992).

B7-3


Evaluation of rough transport loads on the package presented in Part B, Section 7.5, showsthat the package remains fuliy functional, maintains structural integrity, and maintains the contents,the evaluation, package performance is analyzed for both vertical and longitudinal loadings. In bothcases the evaluation shows the induced stresses on the package are below the allowable stresses.

7.3.9 Penetration

The evaluation presented in Part B, Section 7.5, shows the exposed surfaces of the packagecannot be penetrated by a 6.0-kg (13.0-lb) object dropped from 1.0 m (40.0 in.). Results of theevaluation show that only superficial marring of the exposed stainless steel surfaces results fromdropping the object.

7.3.10 Conclusions

The results of these evaluations show the package is acceptable for transport on the HanfordSite under NTC. Due to the possibility of in-leakage of water into the cask cavity, proper protectionand sealing of the.payload and cask internals are required.

7.4 REFERENCES

ANSI, 1980, American National Standard Design Basis for Resistance to Shock and Vibration ofRadioactive Material Packages Greater than One Ton in Truck Transport, DRAFT, ANSI N14.23,American National Standards Institute, New York, New York.

ASME, 1992, Boiler and Pressure Vessel Code, Section VIII, Division 1, American Society ofMechanical Engineers, New York, New York.

Fadeff, J. G., 1992, Environmental Conditions for On-site Hazardous Materials Packages,WHC-SD-TP-RPT-004, Rev. 0, Westinghouse Hanford Company, Richland, Washington.

RL, 1993, Hanford Site Hoisting and Rigging Manual, DOE/RL-92-36, U.S. Department of Energy,Richland Operations Office, Richland, Washington.

B7-4

HNF-SD-TP-SEP-063 DRAFT Rev. 0 May 19, 1997

7.5 APPENDIX: STRUCTURAL ANALYSIS

ENGINEERING SAFETY EVALUATION, , P R T R Cask NTC Structural Evaluation & Puncture Threshold : Page: 1, of II

Originator? S. S. Shiraca jfafp&C--— Date: 05/19/97Checker: R. J. Smith 7<O J?U*&^ Pate: 05/25/97

I. Objective:

The objective of this evaluation is to evaluate the PRTR cask performance relative to the Normal TransportConditions outlined within Section 7 of this Safety Evaluation Packaging (SEP). Also this evaluationdetermines adequacy of lifting system and the equivalent steel thickness of the cask for determination of thepuncture failure threshold.

II. References:

ANSI, 1992, ANSI N 14.23, Draft American National Standard Design Basis for Resistance to Shock andVibration of Radioactive Material Packages Greater than One Ton in Truck Transport, American NationalStandard Institute, New York, New York.

ASME, 1995, Boiler and Pressure Vessel Code, Section II, Part D, American Society of Mechanical Engineers,New York, New York.

Roark, R. J., 1965, Formulas for Stress andStrain, Fourth Edition, McGraw-Hill Book Company, New York,New York.

Blodgelt, O. W., 1966, Design of Welded Structures, The James F. Lincoln Arc Welding Foundation, Cleveland,Ohio.

Roark, R.}., Young, W. C , 1 983, Formulas for Stress andStrain, Fifth Edition, McGraw-Hill Book Company,New York, New York.

ASME, 3992, Boiler and Pressure Vessel Code, Section VIII, Division 1, American Society of MechanicalEngineers, New York, New York.

Rinehart, J. S., and Pearson, 3., 1954, Behavior of Metals Under Impulsive Loads, American Society of Metals,Cleveland, Ohio.

ANSI, 1993, ANSI N14.6, American National Standard for Radioactive Materials-Special Lifting Devices forShipping Containers Weighing 10 000 Pounds (4500 kg) or More, American National Standard Institute, NewYork, New York.

ORNL, 1970, Cask Designer's Guide, ORNL-NISC-68, Oak Ridge National Laboratory, Oak Ridge,Tennessee.

Mathcad Plus 5, 1994, User's Guide, Math Soft Inc., Cambridge, Massachusetts.

III. Results and Conclusions:

This evaluation shows that the PRTR cask will meet normal transport conditions (NTC) and lifting loads asspecified in Section 7 of this SEP. The evaluation shows the incrtial loadings on the cask from rough transportare well below the material yield. Consequently, rough transport will not result in any permanent deformation ofthe package. The results demonstrate that the cask will not sustain any damage during NTC and remain fullyfunctional.

Also, within this evaluation, the equivalent steel thickness of the package is determined. Based on empiricaldata (Rinchart, 1954) the equivalent steel thickness of the cask body is 2.6 inches.

B7-5


ENGINEERING SAFETY EVALUATIONSubject: PRTR Cask NTC Structural Evaluation & Puncture Threshold Page:_2_Originator: S. S. Shirapa V ^ f : Date: 05;Checker: R. J. Smith -fXi^- • Date: 05/

/IV. Evaluation:

Normal Transport Conditions Evaluation of PRTR Cask:

Determination of inertia! loading for NTC:During normal transport of this package no in-transit load transfers are involved. Consequently, normalcondition inertia! loads arise from rough transport shock loads. Rough transport loads are derived from ANSIN 14.23 (ANSI, 1980). Rough transport shock loads for this package are defined as a vertical 3.5 g andlongitudinal (in direction of travel) 2.3 g shock ioad to the package. Lateral load of 1.6 g is neglected, as it isbounded by the vertical and longitudinal loads. Assume the shock is a single pulse applied to the package asa quasi-static toad. Acceptance criteria is the package remain fiilly functional after the event, i. c., no plasticdeformation of components.

Empty weight of package: W p :-• 24001bf Maximum weight of payload: \V p a v ;~ 25(Hbf

Gross weight of package: W t :~ W -i- W p a v

Inertia! loadings: Vertical: g v :~3.5 Longitudinal: g | :"2.3

Material parameters (ASME, 1995):

Assume cask shells are constructed of 3041. stainless steel (SA 240, Class 2) at 200 °F:

Poisson's Ratio: v g s t :~0.31

Elastic modulus: E s s t :-27.6I06-psi

Allowable stress for NTC on sst components based on maximum shear stress: s a s s t :•= —s v s s (

Assumed cask bolts are constructed of SA193TypeB8(Class2)at200 °F:

Yield strength: s y b :-27.5ksi

" "" s a b : ; ; ~ s y b

Assume lead properties at 250 °F:

Yield strength: s ypb : ~ Sksi Poisson's ratio: v b :-0.4

Elastic modulus: E p

Allowable stress for NTC bolts based on ASME criteria:

B7-6


ENGINEERING SAFETY EVALUATIONSubject: PRTR Cask NTC Structural Evaluation & Puncture Threshold Page: 3,. of. .1.1.Originator: S. S. Shirapa j f ^ ^ ' Date: 05/19/97Checker: R. J. Smith '7X/<g~~. Pate: 05/25/97

Geometric parameters of package:

Idealize the package as a composite beam with of concentric cylinders of stainless steel and lead.

' c ' Lcngthofcask: l c ~39.625in

Diameter of cask: d c :- 14in

Length between supports: 1 s : ; 1 c 2(2.5in)

Outer shell wall thickness: t o s : - 0.250 in

d cOutcrshcll outside radius: r ^ :•• — •

Outer shell inside radius: r_; :"r n r t tn-

2

.. 3.12Sin

Inner shell outside radius:

Inner shell inside radius:2

Inner shell wall thickness: t ; s ~ r j 0 - r ;j t ; s = O.I2*in

End plate thickness: t c p • = 0.5-in End plate weld leg: w | e g : " O.I 875in

Determine deflection of lead, assuming the lend is unbonded to the stainless steel walls:

Density of lead: p p b : - 7 I 0 - -

Idealize as ring supporting it's own weiglit. UseRoark, 19(55, case 18, page 176.

Weight per linear inch of lead:

w p b •"Ppb' | i7 t \ roi ' r io /

Moment of inertia of the section:

\ 4roi " r io

.'pb-«—~iroiH

B7-7


ENGINEERING SAFETY EVALUATIONSubject: PRTR Cask NTC Stnicftiral Evaluation & Puncture ThresholdOriginatoTT S. S. Shiraga ^66/Checker: R. J. Smith Alj/-—

Page: 4 of HDate: 05/19/97Date: 05/25/97

f lead: A --—-—P---E-.(0.4674) A =-8.8-10 6 -inDiametrial compression oE p b ' p b

This is negligible, consequently no significant load on inner shell.

Determine leading on Cask Body due to Bending;

Since cask is shipped in the horizontal, setting on two support plates, idealize as simply supported beam withuniform loading which over hangs each end (Biodgett, 1966).

uiuuuuuumimmuiuuiumui

Assumed uniform loac

Reaction loads at supports: F r '

= 234*- - Over hang distance: x: ; ~ -

F r = 4638'lbf

W |Maximum moment at center: M _ :;-~— I . - 4-x M . =34346*lbfin

c c. \ s ; c

Maxitiium load and moment at supports.

Determine composite moment of inertia:

Moment of inertia about center (neutral axis) of cross section:

Outer shell: ]«:=••«- - - " ~ Inner shell: I •„

B7-8


ENGINEERING SAFETY EVALUATIONSubject: PRTR Cask NTC Structural Evaluation &. Puncture ThresholdOriginator: ...S..S...Shirae;a J ^ !Checker: J".R.,',J".Smith jQ&SL~

Composite moment of inertia: ^ ' : "^ss t " ' o s "*' pb ' 'pb ' 1 ^ssf ' is

Determine composite area:

Outer shell: A nc • • n - f r * - rn !2) Innershell: A ic :=«-(r:

Page:,..5_.of_1.1.Date: 05/19/97Date:.05/25/97

Lead shielding: A p b :- n-(roj - r

Composite area factor: AE : = A

A

-t- A pD-EpD -t- A jg-E

Bending stress in outer shell at maximum moment:

Bending stress in inner shell at maximum moment:

Bending stress in lead shielding at maximum momer

Maximum shear stress in outer shell: T s o s : : : -

Maximum shear stress in inner shell:

Maximum shear stress in shielding:

AE

M

EI

131

EI

' s o

•rooa

^ ,

s =0.211s:

, =0.2l*ksi

bos "

bis =

'bpb

i " €

= l3.67-psi

3.29-psi

-0.95-psi

5

^ =0.02"ksiT ^ •"

Since stresses are not significant, package is demonstrated to meet acceptance criteria for vertical loading.

Determine worst case end load:

Assume as a worst case entire weight of cask is inertially loaded onto the end plate, weakest component is theweld. Also assume the plate thickness is uniform and that of the thinnest section.

Idealize as a plate with a center hole, clamped and fixed at outer and inner edges, loaded with a uniformlydistributed load (Roark, 1983, Table 24,2h).

For determination of moments redefine: r:- :~-••'-- • - 0.188 in

Inertial load on end plate assume uniformly distributed: wgrwt _

(r 2-r AVoi rio y

w , =50-psi

B7-9


ENGINEERING SAFETY EVALUATIONSubject: PKTR Cask NTC Structural Evaluation & Puncture Threshold Page: 6 of 11Originator: ...S._S.., .Shiraga.. s%%f Date: 05/19/97Checker: R.J. Smith ,.AJt±zz Date: 05/25/97

, • , ' . . . • > ' , .

\'u

-'/, N"

...vsstM,-vsst) - O 5 p

N< roi/

' o i \ • / ' - *

'r./'T 4

._ I1.14-16

rio'2

roi.

AKiaHoadoninnerweld: 01 \ C2C6 C3C5 i

Axial load on outer weld:l: row riw- : " r ," \'oi rio J fc\ r0i; ^ r0i

Momemoninner^o:P' ° ' I C2C6 C3-C5 /

. . , "•• M i w C 8 .- f i w r o i -C9 - » p l r o i2 - U 7

Axial load from moment on inner weld: fu-.^.'" -—• ^hiw~37*

Moment on outer weld:

ow

M i w

•89'

= 9

M „

Ibfin

4-lbf

... - 63•Ibf

Axial load from moment on outer weld: f i i r ow

B7-10


ENGINEERING SAFETY EVALUATIONSubject: PRTR Cask NTC Structural Bvaluation & Puncture Threshold . Page: 7 of 11Originator: S. S. Shiraca x 4 ^ ? Date: OS/19/97Checker: R. J. Smith /</ ,f^ Date: 05/25/97

Total load on inner weld: f f :w - f ;w^fhiw ft;u,= 181*~tiw"Ibf

Total load on outer weld: f tow ' f o w | l f b o w, Ibf

Determine allowable on welds:

Assuming base material strengths and ASME joint efficiency factors:

Length of inner weld: w -m : r 0.1875in Leg length of outer weld: w o u t :~0.1875in

ASME joint efficiency (ASME, 1992) factor assuming no inspection:, eff: - 0.60

Allowable on inner weld: f iall : ""° - 7 & 7 s ysst 'w in ' e f r fiall = HS94--

Allowable on outer weld: foa!!:~ 0.707s ysst-wol]t-eff foall~ 1694*T"

fj,,.Margin ofsafety on inner weld: MSiw:=—" - 1 MSiw-8.38 i£>

f[jw

fo_|,Margin of safety on outer weld: M S 0 1 1 / ~ - — j ~ ' MSOW=20.26 «^i

Determine end loading of top end closure bolts:

Assume payload is restrained in cavity by dunnage and bears against the top and bottom closures. Worstcase loading would occur at the top closure, since it has the fewest number of bolts. Loading results fromshield plug and payload.

Weight of shield plug, ignore inner plumbing:

Plate diameter, d s p ! --8.75-in Plate thickness: t p ) :70.37Si»

Shell OD: od s h 5.25in Wall thickness: t g h :"0.25Oin Inner plate thickness: t i p | :~0.25in

Inner shell ID: id i s h ' o d s h - 2-tsh Length: l s h ^S.OOin- t i p ]

Lead length: 1 p b := 1 s h Stainless steel density: p s s t :-0.29

B7-11


ENGINEERING SAFETY EVALUATIONSubject: PRTR Cask NTC Structural Evaluation & Puncture ThresholdOriginator: S. S. Shiraga ^0^^ ,Checker: R. J. Smith

Weight of stainless steel:

—t „ , H- asst ' | J

id nh<Weightoflead: W p b ' P p b — " r - ' p b w p b ' 1 H b f

Total plug weight: > l u g : " s s t 1 » pb "plug = 2 s - l b f

Assume bolts are uniformly loaded:

20Nominal diameter of bolts: d b

: "0 .25in Lead: ' b ; ".

0 9743\2

Tensile stress area: A s - 0 . 7 8 5 4 d b - ~ ' ~ Number of bolts: n b o I t : 4

b /

Assume preload torque for bolts is: T p r c :- 30-lbf-in T p r e =2.5*ft*lbf

Assume nut friction factor: \i n r 0.2

Preload force per bolt: F p r e : ~ — " [ - r p r e = 6 0 0 " l b f

Total load on top closure bolts: F d •' n b o l , - F p r e r g | ( w p , n g + W p a y ) F d - 1769-lbf

Tensile stress on bolts: °ten " ^ — a t e n = 13.89'ksi =S3n bolfA s

Margin of safety: MS j ^ , : - — * • - I MS Mt -0.32 - ®"ten

Therefore OK, since margin of safety is positive.

B7-12


ENGINEERING SAFETY EVALUATIONSubject: PRTR Cask NTCgtructiiral Evaluation & Puncture Threshold Page:..9_.of I.I.Originator:. S. S. Sh.i'raga"" jfi/ZS I."....'"".!."""". Pate: 05/19/97.Checker: R. J. Smith ?^4^—' Pate: 05/25/97

Lifting Evaluation:

Determine if the cask lifting yoke meets the 3 to 1 requirements of Hanford Hoisting & Rigging Manual:

Idealize lifting yoke as a short beam uniformly loaded cantilever:

Length of yoke: l y -~0.9375in Diameter of yoke: d y :~l.5739in

\V (Load on yoke: F |o a c J : = ~ - Dynamic load factor: DLF: " 1.25

. 2 . 4V V

Cross sectional area: A v : - i r - - - - Moment of inertia: I v 'r-n-- *•y 4 y 64

/DLF-F,o a d-Iy d yMaximum bending stress at end: a ^ := x..-.J.

\ 'y

Maximum shear stress: xmax'" ~" Tmax='-'''"'(S' " ^3 Ay

Loads are welt under yield strength of material.

Determine if lifting bracket meets requirements of Hanford Hoisting & Rigging Manual:

Cask attachment brackets at yoke:

d v . 4.25in~dEdgedistance: d

e d g e " 3 S m - " Side edge distances: d s i c J e : -•-

Bracket thickness: *brac " ' 'n

DLFF • d

Shear tear out of bracket: o ^ t 0 :: : O(j t 0 ~ 1.24'ksi *=§p

d side' l brae

DLFF|«,HTensile stress on bracket: "bten :""

2 t brae d s i<lc

Lifting bail:

Bail thickness: t ^ j p - l - i n Minimum edge distance: d min:""(5.25-3.5)-in

Assumed diameter of hook: d ^ :- J-in

B7-13


ENGINEERING SAFETY EVALUATIONSubject: PRTR Cask NTC Structural Evaluation & Puncture Threshold Page: 10 of IIOriginator: S. S. Shiraaa ^kf Date: 05/19/97Checker: R°'LSm'ith /^./s* Date: 05/25/97

D L P F l o a d

Shear tear out of bail: ^bailto "r °bailto ~".47*ksi * ^2 ' d min t ba i l

Loads are well under yield strength of material

Check of bofts holding bail and cask yoke brackets together.

Nominal diameter: d ^ :"0.625in Lead: 1^ '•"•- • Number of bolts per leg: n ^ :"3

Yield strength of PH-18-8 bolt ( assumed same as 304 stainless steel):

Tensile stress area of screw: A s : • 0.7854 b

' b' b

Determine If Sufficient Thread Engagement Is Available (Industrial Press, 1992):

Available thread depth: ^ avail' 1-5-in Number of threads per in: n

DLFF, o a d

Minimum tensile strength of bolt: s bolt ^ s bol t = ^* ' < s ' "^

nVAs

Maximum minor diameter of internal thread: K n m a x: " 0.546in

Minimum pitch diameter of external thread: Es m j n : O.S561in

Minimum engagement length since materials are the same:

2-A s

n m K | ^ t ( E ! m i n - Knma>[)j

Since Lavail>Le, there is sufficient thread engagement and bolt strength.

NTC Penetration of Package:

Mass of projectile: m_ =6-kg Height of drop: h ^ :- 1-m Hemispherical end diameter: d i i e n i j ' -3.2-cm

Evaluate package penetration by empirical methods (Uhinehart and Pearson, 1954):

Velocity of projectile: v 0 : = 2-g-h d r v 0 = 14.5---

B7-14


ENGINEERING SAFETY EVALUATIONSubject: PRTR Cask NTC Structural Evaluation & Puncture Threshold Page: II of IIOriginator: S. S. Shiraea . ^ f Date: 05/11111Checker: R.) . Smith ~^M Date: 05<25/97

/Assuming the test rod is a hard unyielding object, at this velocity (< 10,000 ft/sec), the force that acts onthe projectile is proportional to the cross sectional area and is essentially constant during penetration.

4 •'

Volume of material displaced per unit of energy constant (Rhinehart and Pearson, 1954, page 202, Table 12-1):

1 •> K sDepth ofpenetration into steel: s s p :- '—mp-v0 s s p =O.00Hn =@p

2 A p

The penetration depth is not significant, therefore no penetration of package.

PRTR Cask Puncture Failure Thresholds, J^ujvalM-StecLTliicKness:

Equivalent Thickness of lead to steel (Rinehart, 1954): f "-• 2.3

ID of Outer Shell: id o 3 " 13,5-in Outer Shell Wall Thickness: t o w 3 :- 0.25in

OD of Inner Shell: od i 3 :--3.375in ID of Inner Shell: id i 3 : - 3.125in

od ••>- id J3Inner Shell Wall Thickness: l iw3 :" l iw3 = 0 ] 25* in

id o 3 - od i 3Lead Thickness: t p b 3 -~ t b 3 =5.06*in

Total Equivalent thickness of steel: t ^ :" * Ow3"'' * itv3"*—^ "Ow3"'' * itv3"*—^ "" leq3 =

B7-15



B7-16


8.0 THERMAL EVALUATION

8.1 INTRODUCTION

The PRTR Graphite Cask is an onsite, intra-area packaging for transporting Type B radioactivematerial within the 300 Area of the Hanford Site. This section of the document defines and evaluatesthe NTC structural requirements for intra-area transport of this package. Thermal performance of thepackage is evaluated only for NTC; accident conditions are evaluated in the risk and dose consequencesection of this document.

8.2 THERMAL EVALUATION OF PACKAGE

8.2.1 Package Description

The PRTR Graphite Cask is fundamentally a right circular cylinder of lead and stainless steelcomposite construction. The lead is sandwiched between outer and inner stainless steel tubular shells.At each end of the cask is a thick circular plate that is welded to both inner and outer shells, whichencapsulates the lead. At the top, closure of the inner cavity is provided by a bolted blind flange withan attached shield plug of.composite lead-stainless steel construction. The cask is equipped with amanually actuated, sliding trap door, which provides closure at the bottom end. None of the endclosures are sealed. A handling yoke is provided on the cask and welded to the outer shell. Inaddition, support plates are welded to the outer housing of the cask to provide support during transportand lifting attachment anchors for handling.

The cask is constructed of welded 304L stainless steel. Shielding is provided by lead, which ispoured after fabrication of the stainless steel body and internal components.

8.3 NORMAL TRANSPORT CONDITIONS THERMAL EVALUATION


Thermal performance of the package is assessed for Hanfbrd Site NTC in this section. Thepackage is evaluated for the worst-case Hanford Site thermal loading condition of a still-air ambienttemperature of 4-6 °C (115 °F [Fadeff 19921) with decay heat sources with and without solarinsolation. Because of the variability of the payloads, the heat sources are assumed to be tightlypacked in the cask cavity and against the inside wall of the cask.


The criterion for acceptable performance of the package is the accessible surface of thepackage in still air at 46 °C (115 °F) and in the shade is not to exceed 82 °C (182 °F). This is basedon this package being transported as an exclusive-use shipment.

8.3.3 Thermal Evaluation and Conclusions

For this evaluation the worst-case decay heat source is assumed to generate a total heat loadof 5.65 W. Based on the variable geometries of the payloads, the configuration of the heat source isassumed to be uniformly distributed over the length of the cask cavity and fitted tightly up against theinside wall of the cavity. This provides a conservative estimate of the cask temperature, but it does

B8-1


not provide a conservative estimate of the temperature load to the payload. This evaluation boundstemperatures for the cask, but does not provide any estimation of payload temperatures. Temperature-sensitive payloads must be evaluated on a case-by-case basis to determine the temperature parameterswithin the cask.

Results of this evaluation show the cask component temperatures under solar insolation arebelow 99 °C (211 °F) for the structural evaluation. The results also show the cask meets the NTCexterior surface temperature requirement of 82 °C (182 °F) in the shade for exclusive-use shipments.Table B2-2 shows a heat loading of 2.92 W resulting from a reduced payload. Because the heatloading is less than the previously analyzed heat loading, the thermal evaluation conclusion remains thesame.

8.4 REFERENCE

Fadeff, J. G., 1992, Environmental Conditions for On-site Hazardous Materials Packages,WHC-SD-TP-RPT-004, Rev. 0, Westinghouse Hanford Company, Richland, Washington.

B8-2


8.5 APPENDIX: PRTR GRAPHITE CASK NTC THERMAL EVALUATION

ENGINEERING SAFETY EVALUATIONSubject: PRTR Cask Normal Ttansgortgonditions Thermal Evaluation Page:_l_ofVSOriginator: S. S. Shiraga . ^ 9 % . ? 1 = ^ S - . . Date: 05/20/97Checker: S. R. Crow. *f\, /£ (U**) Date: 05/25/97

I. Objective:

The objective of this evaluation is determine the cask component temperatures under solar insolation for thestructural evaluation and the exterior temperature in the shade as specified in Section 8 of this Safety Evaluationfor Packaging (SEP).

II. References:

Irwin, J. J., 1995, WHC-SD-TP-RPT-005, Rev. 1, Thermal Analysis Methods for Safety Analysis Reports forPackaging, Westinghouse Hanford Company, Richland, Wash.

ORNL, 1970, Cask Designer's Guide, ORNL-NISC-68, Oak Ridge National Laboratory, Oak Ridge,Tennessee.

Mathcad Plus 5,1994, User's Guide, Math Soft Inc., Cambridge, Massachusetts.

WHC, 1980, Drawing No. H-3-13699, Rev. 7, PRTR Graphite Sample Cask Assy., Westinghouse HanfordCompany, Richland, Washington.

III. Results and Conclusions:

The results also show the cask meets the normal transport conditions (NTC) exterior temperature requirement of182 °F in the shade for exclusive use shipments. Because of the variability of the payloads, the heat sources areassumed to be tightly packed in the cask cavity and against the inside wall of the cask. This provides aconservative estimate of the peak temperatures subjected to the cask, but it does not provide a conservativeestimate of the payload temperatures. Temperature sensitive payloads must be.evaluated on a case by case basisto verify payload stability and integrity.

B8-3


ENGINEERING SAFETY EVALUATIONSubiect: PRTR Cask Normal Transport Conditions Thermal EvaluationOriginator: S. S. ShiragaChecker: S. R.

Page: 2 of 5

IV. Evaluation:

Normal Transport Conditions (NTO Thermal Evaluation:

Determine temperature of outer shell with and without solar insolation:

Evaluate as steady state heat transfer for a horizontal cylinder with flat plate ends (Irwin, 1995):

BTU

hr-ft2

. . « ^ B T U

Free convection coefficient for a horizontal cylinder:

Free convection coefficient for a vertical plate:hr-ft2

S u r f a c e A ,

Length of cylinder: I_:=39-in Diameter of plate: d c := 14-in

Surface area of cylinder: Ac :=rc-lc-dc Surface area of plate: A ^ : = — d c

Convection coefficients: h d . hd, :=_k v p -2-A b -R 4

B8-4


ENGINEERING SAFETY EVALUATIONSubject: PRTR Cask Normal Transport Conditions Thermal Evaluation Page: 3 of 5Originator: S. S. Shiraga ^*6£S • p a t e ; 05/20/97Checker: S.R.Crow £ V ^ . Date: 05/25/97

Radient heating constant:

Stefan-Boltzman's natural constant:hr-ft2-R4

Emissivity of stainless steel: es:=0.32

Radiation coefficients Kj :~^sb'S S-A c K2:-Gsh-ss-2-/

Solar heat loading (Irwin, 1995), hourly average loading based on a 12 hr period:

Curved surfaces: Q s l : = 3 1 4 — Q s l = 9 9 . 5 4 ' ^ ^m2 hr-ft2

Non-vertical surfaces, flat surfaces: Q s := Q s =49.77*

2 hr-ft2

Internal heat load: q !n t :=5.65watt •=&

Assumed solar absorptivity: a s o j -=0.57

Solar heat load: q so l : = a s o i - [ Q s - — + Q s i - A c

BTT JTotal heat load: q t o t :=q s o l + q i n t q t o t = 7 1 0 - - —

nr

Outside ambient temperature is 115 °F and in Rankine: T 0 •= (115+ 459.7)-R

Using conservation of energy: q ;n - q o u t = 0

B8-5


ENGINEERING SAFETY EVALUATIONSubject: PRTR Cask Normal Transport Conditions Thermal Evaluation ; Page: 4 of 5Originator: S. S. ShiragaChecker: S. R. Crow

Solve for Tfwhich the temperature at the surface using MathCad roots of equation solution:

Tfl:=root[qtot-Kr(Tf4-To

4)-K2.(Tf'1-To

4)-hd1-(TrTo)4-hd2.(Tf-To)4>TfJ

Date: 05/20/97Date: 05/25/97

External surface temperature in sun:

Tf,-459.7RJTemperature in °F: T ff:=

Temperature ia Shade:

Total shaded heat load: 1 s t o t ' ^ int

Solve for Tf which the temperature at the surface using MathCad roots of equation solution:

External surface temperature in shate: T ^ = 577*R

T C -459 .7RTemperature in °F: T ff2:=

R

With this simplified model determine temperature of inner shell with solar insolation:

Assume as one-dimensional heat transfer and internal heat source is against inside shell wall, no gap.

In — In — In —r 2

r lIn

r 2 r 3

B8-6


ENGINEERING SAFETY EVALUATIONSubject: PRTR Cask Normal Transport Conditions Thermal Evaluation Page: 5 of 5Originator: S. S. Shiraga s?j£^ Date: 05/20/97

. Date: 05/25/97Checker: S. R. Crow

Inner shell inside radius: r j := 3A25m

Inner shell outside radius: r *> '-=._ 3,375in

. . 13.5inOuter shell inside radius: r 3 '=

Outer shell outside radius: r / := —

Outer shell temperature, for full solar insolation:

Thermal properties of materials:

Conductivity (Irwin, 1995):

Leadat212»F: . k D b :=0.000447-^±f- 304L stainless steel at 200 »F: k s s t :=0.000215-5if-

Solve heat transfer equation for inner temperature:

1 t o t + 2"' t-

- I n - In

Inside temperature of inner shell (°F): T j = 2 1 1

B8-7



B8-8


9.0 PRESSURE AND GAS GENERATION EVALUATION

Only dry contents are authorized for the PRTR Graphite Cask. Therefore, there are no pressureor gas generation concerns.

B9-1



B9-2


10.0 TIEDOWN EVALUATION

10.1 SYSTEM DESIGN

The PRTR Graphite Cask shall be centered and placed horizontally on the bed of the trailer forshipment. The long axis of the cask is centered along the long axis of the trailer. In accordance withthe regulations, the tiedowns must have an aggregate working capacity of one-haif the cask weight.

The package is to be secured in accordance with DOT regulations (49 CFR 393.100}. The caskis to be secured to the trailer by two sets of tiedowns as shown in Figure 10-1. One set acts aschocks to block and brace the cask from horizontal movement. The other set acts as verticalrestraints. There are two 4x4 wood blocks placed at each end of the cask. These 4x4 blocks have a2x2 nailed to the side at the bottom to form landings for the tiedowns. Each of the chocking tiedownsis looped around the cask from opposite sides of the trailer and attached to the trailer. The chockingtiedowns lay on the landing and bear against the wood blocks when drawn tight. The vertical restrainttiedowns are placed over the cask on each side of the lifting yoke. These tiedowns are then attachedto the trailer on opposite sides and drawn tight.

Figure 10-1. Cask Tiedown Configuration.

4X4 Wood Block -

SXS Wood BlockNailed lo 4X4

B10-1


10.2 ATTACHMENTS, RATINGS, AND REQUIREMENTS

Each tiedown and trailer attachment point must have a minimum working strength of11,120 N (2,500 Ib). The 2x2 wood blocks must be nailed to the 4x4 wood blocks with a minimum ofthree 10 d nails. The length of the blocks is specified as the same as the diameter of the cask towithin a tolerance of 0.32 cm (Vs in.).

10.3 REFERENCE

49 CFR 393.100, 1997, "Parts and Accessories Necessary for Safe Operation," Code of FederalRegulations, as amended.

B10-2


10.4 APPENDIX: ENGINEERING SAFETY EVALUATION

ENGINEERING SAFETY EVALUATION

Subject: 327 PRTR Cask Tiedown Evaluation Page 1 of 3Preparer: S. S. Shiraaa \4J.rff— //st/ _ _ Date 07/21/97Checker: P. C. Ferrell Porf- C. <C^ny^/' Date #fr~/f 7Section Chief: S. S. Shiraaa s&fr&~>SsSZ—_ Date_

1.0 OBJECTIVE

The objective of this evaluation is to determine the capacity and configuration of the tiedownsystem for the 327 PRTR Cask. The tiedowns are specified to the requirements of 49 CFR393.100.

2.0 REFERENCES

49 CFR 393.100, 1995, "Protection Against Falling Cargo," Subpart I, Code of Federal Regulations, asamended.

3.0 ASSUMPTIONS, RESULTS, AND CONCLUSIONS

As defined in this document, shipment of the 327 PRTR cask within the 300 Area isauthorized under a risk based assessment. Consequently, the tiedown system must be anengineered system to ensure that the package remains on the conveyance during all normalnon-accident conditions. Since the shipment is only within the 300 Area, the system isspecified based on the requirements of 49 CFR 393.100.

As shown in the evaluation, the cask is assumed to be centered on a standard flat bed trailerand the lifting yoke placed in the vertical position. The system consists of two 4X4 woodblocks with 2X2 wood blocks nailed to them, forming an "L" shape. These "L" shaped blocksspan the width of the cask and are placed at each end. Two cables or chains are loopedaround the cask and blocks from each side and drawn tight. The cables or chains rest on thelanding formed by the "L" shape of the blocks. This forms the blocking and bracing to restrainlongitudinal and lateral loads. Placed over the cask on each side of the lifting yoke are twotiedown straps, cables, or chains to provide vertical restraint. The minimum specified workingstrength of the tiedowns is 2,500 Ib. The wood blocks are to be constructed from standardcommercial grade lumber. The 2X2 blocks are to be nailed to the 4X4 blocks With a minimumof three 10 d nails.

WMNW-PE-001/2

B10-3



Subject; 327 PRTR Cask Tiedown EvaluationPreparer: S. S. ShiraqaChecker: P. C. FerrellSection Chief: S. S. Shiraqa

. Page 2 of 3Date 07/21/97Date y//Date <?/x/(7

4.0 EVALUATION

PRTR Cask Tiedown Evaluation:

OD of cask: od c a s k := 14-in Length of cask: 1 c a s k :=39.625in

Gross weight of cask: w c a s k :=26501bf DOT inertial load factor: g ( j o t : = 0.5

Chain height from deck: h ^ ^ l . ^ i n Length to trailer attachment: 1 := 15-in

Loadontiedowns: F ch : = Sdofwcask Fch = 1 3 2 5 # I b f

Tiedown. 1

• 1 . Tiedown £

-iHi--iili

JL 1L

Tiedown 3

TiedoTm 2

BiTfodOTms lfcg go aronnd cask |

WMMW-PE-001/2

B10-4



Subject: 327 PRTR Cask Tiedown EvaluationPreparer:Checker:

S.P.

Section Chief:

S.C.

S

Shiraaa x ^ "Ferrell fP/f-. S. Shiraqa ^ ^

Page 3 of 3Date 07/21/97DateDate

Angle offhorizontal: a := atan

od48-in--

cask

ce=69.9-deg

Angle off vertical: P : = atan •/h b-cos(a)

I ' tP=2Meg

Determine chocking tiedowns:

Tension on lateral chain only one tiedown acting: T | a t := —r c h

sin(a)-cos(P)

Tension on longitudinal chain, two tiedowns acting: T | o ng : =r c h

2(cos(a)-cos(P))

Determine tiedowns:

Vertical tiedown angle: y :=atan

Tension in vertical tiedowns: T

od cask4-ft

y = 16.3'deg

• c h

2-sin(y)

Based on above, minimum working load of all tiedowns is specified as 2,500 Ib.

t = 1412-lbf

WMNW-PE-001/2

B10-5

DISTRIBUTION SHEETTo

Distr ibut ion

From

Packaging Engineering

Project Title/Work Order

Safety Evaluation for Packaging (Onsite) Plutonium Recycle TestReactor Graphite Cask (HNF-SD-TP-SEP-063, Rev. 0) .

Name MSINText

With AllAttach.

Page 1 of 1

Date Sept. 24, 1997

EDT No. 621885

ECN No. N/A

Text Only Attach./Appendix

Only

EDT/ECNOnly

R. L.. ClawsonJ. G. FieldC. R. HooverS. B. Johnston

HNF-SD-TP-SEP-063 Fi leP97-046 (D. Kelly)

Central Files

Hl-14 XHl-15 XHl-15 XLl-03 X

Hl-15 XHl-15A3-88 X

A-6000-135 (01/93) WEF067

1edt621885 - international nuclear information system (inis)

Documents