regional training course on the safe transport of radioactive material in the caribbean module 2.4...

Regional Training Course on the Regional Training Course on the Safe Transport of Radioactive Material in the Safe Transport of Radioactive Material in the

CaribbeanCaribbeanModule 2.4Module 2.4

Transport Package Types and Material Classification

Paul Gray

June 3 2014Panama

19 April 2023Contents

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OverviewOverview

2

1. The classification and selection of materials and package types

2. The main requirements for package types

3. Flow diagram for classification of radioactive material into appropriate UN number

4. Summary


END

“Packaging” and “Packages” are terms of vital importance in Transport Regulations

• Package - The packaging with its radioactive contents as presented for transport

• Packaging - The assembly of components necessary to enclose the radioactive contents completely

+ =

PACKAGING PACKAGE

RADIOACTIVECONTENTS


END

Package Type Options for Transporting Radioactive Material

• Excepted packages• Industrial packages

Types IP-1, IP-2, IP-3• Type A packages• Type B packages• Type C packages• Other (Fissile, UF6)

RAM classified as LSA-I or SCO-I

may also be transported unpackaged

- This presentation will focus on Type A packages


END

GRADED APPROACH TO TRANSPORTGRADED APPROACH TO TRANSPORT

Package integrity is a function of the potential hazard of the contents and the response of a package under •routine conditions of transport (incident free) – represented by general design requirements for all package types,•normal conditions of transport (including minor mishaps) represented by Type A tests and•accident conditions of transport (severe accidents) represented by Type B tests

to assure the same level of safety for all types of packages

Excepted Package Type A Package Type B Package


END

Basic safety functions of packages for Basic safety functions of packages for radioactive materialradioactive material

Hazards of the radioactive Material

Safety functions of the Packaging

Radiotoxicity(Contamination,Incorporation)

Radiation(α, β, γ, n-Radiation)

Heat release

Criticality

Shielding

Containment

Heat transfer

Criticality Safety

6


END

Concept of a Safe Package – Graded ApproachConcept of a Safe Package – Graded ApproachThe greater the hazard the stronger the packageThe greater the hazard the stronger the package

7(Paras of IAEA Regulations TS-R-1, 2009)


END

Excepted Package

• Radioactive material in limited quantity (fractions of A1/A2) representing low hazard

• meets general design requirements to withstand routine conditions of transport

• Surface dose rate ≤ 5 μSv/h

• Only marking with UN number, consignor/consignee (mass > 50 kg)

• No competent authority (CA) approval necessary but the consignor must , on request, make available for inspection by the relevant CA, documentary evidence of the compliance of the package design with all applicable requirements


END

UN Numbers for Excepted PackageUN Numbers for Excepted Package

9

Excepted package

UN 2908 RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - EMPTY PACKAGING

UN 2909 RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - ARTICLES MANUFACTURED FROM NATURAL URANIUM or DEPLETED URANIUM or NATURAL THORIUM

UN 2910 RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - LIMITED QUANTITY OF MATERIAL

UN 2911 RADIOACTIVE MATERIAL, EXCEPTED PACKAGE - INSTRUMENTS or ARTICLES


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Quantities of Radioactive Material in Excepted Packages (UN 2910 and 2911)

Solids:

special form 10-2A1 A1 10-3A1

other form 10-2A2 A2 10-3A2

Liquids 10-3A2 10-1A2 10-4A2

Gases

tritium 2 x 10-2A2 2 x 10-1A22 x 10-2A2

special form 10-3A1 10-1A1 10-3A1

other forms 10-3A2 10-2A2 10-3A2

Physical State Instrument or article Materialsof contents Item limits Package limits Package limits

ACTIVITY LIMITS UN 2911 UN 2910


END

Quantities of Radioactive Material in Excepted Packages (UN 2909 and 2908)

UN 2909: Unlimited quantities of manufactured articles• natural uranium• depleted uranium• natural thoriumIf enclosed in an inactive sheat

UN 2908: Empty packaging, which had previously contained radioactive material and for which the internal non-fixed contamination does not exceed 400 Bq/cm² (beta-/ gamma emitters) and 40 Bq/cm² (alpha-emitters) (100 times the external surface contamination limits for all packages)


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• Designed in relation to its mass, volume and shape to be easily and safely transported and properly secured during transport

• Only external features intended for lifting are available during handling• The external surfaces can be easily decontaminated• The external surfaces shall not retain water• Capable of withstanding the effects of acceleration, vibration and vibration

resonance which may arise under routine conditions of transport• Materials of construction, components and structures shall be physically

and chemically compatible• All valves should be protected against unauthorized operation• The design shall take into account ambient temperatures and pressures

that are likely to be encountered in routine conditions of transport

Medical radioisotope excepted package

General Design Requirements for Excepted Packages


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Industrial Package Type IP-1, IP-2, IP-3

• Mainly used for radioactive waste transport

• Radioactive material must be classified as Low Specific Activity (LSA) material or Surface Contaminated Objects (SCO)

• design requirements for excepted packages + parts of design requirements to withstand normal conditions of transport (Type A package)

• Surface dose rate ≤ 2 mSv/h (dose rate at 2 m distance ≤ 0.1mSv/h)

• Dose rate at 3 m distance from unshielded LSA/SCO contents ≤ 10 mSv/h

• All marking and labelling requirements applicable



END

LSA-I

• Uranium and thorium ores

• Natural uranium, depleted uranium, natural thorium or their compounds, unirradiated in solid or liquid form

• Radioactive material for which A2 value is unlimited (excluding fissile material)

• Other radioactive material in which the activity is distributed throughout and the estimated average specific activity is 30 times the exempt activity concentrations listed in IAEA SSR-6, Table 2

Low Specific Activity (LSA) Material

LSA material shall mean radioactive material which by its nature has a limited specific activity, or radioactive material for which limits of estimated average specific activity apply. External shielding materials surrounding the LSA material shall not be considered in determining the estimated average specific activity.


END

LSA-II• Water with a tritium concentration 0.8 TBq/L

• Other material with average specific activity 10-4A2/g for solids and gases, and 10-5A2/g for liquids

LSA-III

• Solids (eg consolidated wastes, activated materials) – not powders!

• Radioactive material distributed throughout a solid (essentially uniformly distributed)

• Relatively insoluble, under loss of packaging the loss of radioactive material by leaching in water would be 0.1A2 in 7 days

• Estimated average specific activity of the solid (excluding shielding material) 2 x 10-3A2/g

Low Specific Activity (LSA) Material (cont.)


END

A solid object on which:

• the non-fixed contamination on 300 cm2 accessible surface 4 Bq/cm2 for beta and gamma emitters and low toxicity alphas or 0.4 Bq/cm2 for all other alpha emitters

• The fixed contamination on 300 cm2 accessible surface 4 x 104 Bq/cm2 for beta and gamma emitters and low toxicity alphas or 4 x 103 Bq/cm2 for all other alpha emitters

• The non-fixed contamination plus the fixed contamination on 300 cm2 accessible surface 4 x 104 Bq/cm2 for beta and gamma emitters and low toxicity alphas or 4 x 103 Bq/cm2 for all other alpha emitters

Surface Contaminated Object (SCO)

Surface contaminated object (SCO) shal mean a solid object which is not itself radioactive but which has a radioactive material distributed on its surfaces

SCO-I


END

A solid object on which the non-fixed or fixed contamination on 300 cm2 accessible surface exceeds SCO-I limits, were;

•The non-fixed contamination on 300 cm2 does not exceed 400 Bq/cm2 for beta and gamma emitters and low toxicity alphas or 40 Bq/cm2 for all other alpha emitters

•The fixed contamination on 300 cm2 accessible surface 8 x 105 Bq/cm2 for beta and gamma emitters and low toxicity alphas or 8 x 104 Bq/cm2 for all other alpha emitters

•The non-fixed contamination plus the fixed contamination on 300 cm2 accessible surface 8 x 105 Bq/cm2 for beta and gamma emitters and low toxicity alphas or 8 x 104 Bq/cm2 for all other alpha emitters

Surface Contaminated Object (SCO) (cont.)

SCO-II


END

UN Numbers for LSA Material and SCOUN Numbers for LSA Material and SCO

18

Low specific activity radioactive material

UN 2912 RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-I)

UN 3321 RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-II)

UN 3322 RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-III)

UN 3324 RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-II), FISSILE

UN 3325 RADIOACTIVE MATERIAL, LOW SPECIFIC ACTIVITY (LSA-III), FISSILE

Surface contaminated objects

UN 2913 RADIOACTIVE MATERIAL, SURFACE CONTAMINATED OBJECTS (SCO-I or SCO-II)

UN 3326 RADIOACTIVE MATERIAL, SURFACE CONTAMINATED OBJECTS (SCO-I or SCO-II), FISSILE


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Type IP-1 package requirements

• Excepted package requirements, plus

• The smallest overall dimension shall not be less than 10 cm


• Type IP-1, plus

• Loss or dispersal of contents would be prevented and no more than 20% increase in the maximum surface dose rate at any external surface when subjected to:

– A free drop from a height of 0.3m to 1.2m (depending on package mass)

– Stacking test (24 hours), the greater of 5 times package mass or 13kPa x vertically projected area

Design Requirements for Industrial Packages Type IP-1, IP-2, IP-3


END


• Type IP-1, plus

• A security seal to indicate the package has been opened

• Tie down attachments

• Take account of component temperatures ranging from -40ºC to +70 ºC

• Design and manufactured in accordance with national and international standards

• Positive fastening device on containment system

• Retain contents under a reduction of ambient pressure to 60 kPa

• When subjected to water spray test, followed by free drop test, stacking test and penetration test (normal conditions of transport), loss or dispersal of contents would be prevented and no more than 20% increase in the maximum surface dose rate at any external surface (equivalent to Type A package for solids)

Design Requirements for Industrial Packages Type IP-1, IP-2, IP-3 (cont.)


END

Radioactive contents

Industrial package type Exclusive use Not exclusive use

LSA-I

Solid

Liquid

Type IP-1

Type IP-1

Type IP-1

Type IP-2

LSA-II

Solid

Liquid and gas

Type IP-2

Type IP-2

Type IP-2

Type IP-3

LSA-III Type IP-2 Type IP-3

SCO-I Type IP-1 Type IP-1

SCO-II Type IP-2 Type IP-2

Requirements for Industrial Package Types and LSA/SCO contents


END

LSA and SCO in Industrial Packages

Activity limit for

Conveyances Hold (inland waterway)

LSA-I No limit No limit

LSA-II and LSA-IIINon-combustible solids

No Limit 100 A2

LSA-II and LSA-III Combustible solids and all

liquids and gases

100A2 10A2

SCO 100A2 10A2

Conveyance Limits for LSA/SCO in Industrial Packages


END

Type A and Type B Packages Type A and Type B Packages

Type A Package

• small volume of radioisotope

• small package dimension and weight

• transported by air and locally by truck

• Hospitals, clinics, health centers primary customers

Type B Package

• larger dimensions, weight and radioisotope volume

• Radiopharmaceuticals to radiopharmacies or intermediate processors who prepare unit doses

- air shipments primarily but also road


END

Type A Package

• Radioactive contents ≤ A1 or A2

• meets Type A package design requirements to withstand normal conditions of transport





END

- Type A packages for shipping smaller amounts of medical isotopes, such as individual formulations

• ~80% of all medical isotope shipments shipped in Type A packages


END

Layers of protection (Type A)Layers of protection (Type A)

Security tape Packing tape Cardboard box Styrofoam for impact and

penetration protection Lead pot for shielding Absorbent material Vial


END

Basic Radionuclide Values for Transport of Radioactive Material

Radionuclide (atomic number)

A1 (TBq)

A2 (TBq)

Activity concentration

for exempt material

(Bq/g)

Activity limit for

an exempt consignment

(Bq)

Am-241 1 x 101 1 x 10-3 1 x 100 1 x 104

Co-60 4 x 10-1 4 x 10-1 1 x 101 1 x 105

I-129 Unlimited Unlimited 1 x 102 1 x 105

The basic radionuclide values are to be found in Table 2 of SSR-6. For example:

A1 for special form radioactive material (Special Form Certificate)

A2 for all other forms


END

UN Numbers for Materials in Type A UN Numbers for Materials in Type A packagespackages

28

Type A package

UN 2915 RADIOACTIVE MATERIAL, TYPE A PACKAGE

UN 3327 RADIOACTIVE MATERIAL, TYPE A PACKAGE, FISSILE

UN 3332 RADIOACTIVE MATERIAL, TYPE A PACKAGE, SPECIAL FORM

UN 3333 RADIOACTIVE MATERIAL, TYPE A PACKAGE, SPECIAL FORM, FISSILE


END

• Type IP-3 for solids, plus• If designed to contain liquid radioactive material, the free drop test will be from a

height of 9m onto an unyielding target followed by a penetration test from an increased height of 1.7m

• The design shall include sufficient absorbent material to absorb twice the volume of liquid contents, or must have a containment system composed of a primary inner and secondary outer containment components designed to enclose and retain the liquid contents

• For packages designed to contain gases, the package shall prevent loss or dispersal (tritium and noble gases are excepted)

• When subjected to water spray test, followed by free drop test, stacking test and penetration test (normal conditions of transport), loss or dispersal of contents would be prevented and no more than 20% increase in the maximum surface dose rate at any external surface

Design Requirements for Type A Package

Type A package (after 9m drop test)


END

Type A Tests to Simulate Normal Conditions of Transport

– Water spray test– Free drop test on unyielding

target– Stacking test– Penetration test

Resulting in the most damaging effect to the package


END

Water Spray Test for Type A packages

• Simulates rainfall at rate of 50 mm/h

• Applied for one hour• Package allowed to soak to

maximum extent prior to next test

• Intended for packages utilizing fiberboard

• May be omitted (reasoned argument) if package materials are clearly not vulnerable to this test

Para. 721


END

Free Drop Test for Type A Packages

• Simulates drops during normal transport• Specimen dropped so as

to cause maximum damage

• Dropped onto flat,unyielding target

• Height of drop is graded

– 1.2 m if package <5000 kg– 0.9 m if package > 5000 kg, < 10 000 kg– 0.6 m if package > 10 000 kg, <15 000 kg– 0.3 m if package > 15 000 kg

Para. 722


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Stacking Test for Type A Packages

• Intended to ensure effectiveness of package in static compression loading

• Specimen required to withstand for 24 h– 5 times package weight

stacked on top, or– 13 kPa (0.13 kgf/cm2)

multiplied by the vertically-projected area of the package

whichever is greater

Para. 723


END

Penetration Test for Type A Packages

• Uses a 6 kg non-deformable bar with 32 mm diameter hemispherical head

• Dropped onto package from height of 1 m

• Direction/point of impact must assure maximum potential damage

Para. 724

Simulates objects falling onto package, impact from loading hooks or forklifts, without loss of contents


END

Type B Package

• For large quantities of radioactive material as approved by the CA

• meets Type B package design requirements to withstand accident conditions of transport



• Subject to CA approval and package design approval certificate as Type B(U) or Type B(M) package issued by CA

• Type B tests to simulate accident conditions of transport


END

Type B Packages (F-458)Type B Packages (F-458)

Type B(U) container can weigh 125 kg - 167 kg.

Shipping molybdenum-99, used ultimately in some 80% of all nuclear medicine or diagnostic scans. Also used for I-131


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Transport PackagingTransport Packaging

Thermal and impact protection

some shielding

10”

7.25”2.75

4”

19.4”

15.8”

OverpackShielding

VesselLeak Proof

Insert

Radioactive shielding Containment of isotope


END

Layers of protection (Type B)Layers of protection (Type B)


END

39

Cobalt - 60

Cobalt-60 pencils emit gamma radiation - this energy is harnessed to eliminate pathogens and microbes

Cobalt-60: - A solid metal - Non-fissionable - Non-soluble - Non-dispersible - Non-flammable - Long half life - Large quantities per container - Sources and containers licensed - 5.25 year half-life


END

At least one dimension not less than 5mm

No break or shatter under

• Impact test – free drop from a height of 9m

• Percussion test – drop a 25mm diameter bar, 1.4 kg mass, from 1m height

• Bend test – minimum length 10cm, rigidly clamped in horizontal position with half length exposed

No melting or dispersal in the heat test – 800 ºC for 10 minutes

Example: Special Form in a Type A package– A2 (0.6 TBq Cs137)

– A1 (2 TBq Cs137 Special Form)

Special Form Requirements

Special form radioactive material shall mean either an indispersible solid radioactive material or a sealed capsule containing radioactive material


END

41

Sea Freight Container Handling

Containers must be able to withstand worst-case potential accident conditions


END

42

F-168: A Type B(U) Package

Large dimensions, weight and radioisotope holding capacityCobalt-60 to sterilization facilities: - ports for export to overseas destinations - road/ocean/rail shipments


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43

F-168 Package: Layers of Protection

54.0 in. (1372 m m )

39.88 in. (1013 m m )

57.3

1 in

. (14

56 m

m)

8.0

in.

(203

mm

) (203

mm

)

8.0

in.

Steel-covered insulated fire shields for thermal protection

Steel fins dissipate heat during normal conditions of transport and provide impact protection

11 inches (270 mm) of lead shielding, encased in steel for radiation protection

Cage containing double-encapsulated sealed sources

Weight: 5,445 kg (12,000 lbs)


END

44

F-168 Container Design – Shielding


END

45

F-168 Container Design - Plug


END

Type B content limits• The content limit is as defined in the package design safety case which is

submitted to the competent authorities for assessment and approval

Type B package requirements• Type A, plus• Capable of operating in ambient temperatures of -40ºC to +38 ºC • Be capable of being left unattended for one week in an ambient of 38ºC plus

insolation at equilibrium thermal conditions

– with the heat generated by radioactive contents – package continues to meet its applicable requirements for

• containment, • shielding, and • criticality control (fissile contents)

Design Requirements for Type B Package


END

• Restrict the loss of radioactive contents to 10-6A2 per hour when subjected to Type

A tests

• Restrict the loss of radioactive contents to A2 in a week when subjected to Type B

tests:– A free drop test from 9m onto an unyielding target– A penetration test– A fully engulfing fire test of 800ºC for 30 minutes– A water immersion test of 15m for a minimum of 8 hours– A water immersion test of 200m for 1 hour ( >105 A2 )

• A maximum normal operating pressure of 700 kPa (gauge)

Design Requirements for Type B Package (cont.)


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Classification of Radioactive MaterialClassification of Radioactive Material

48

Radioactive material should be classified andassigned under the appropriate UN number and associated proper shipping name

The UN number assigned depends on - the activity level of the radionuclides contained in the package, - the fissile or non-fissile properties of these radionuclides, - the type of package, and - the nature or form of the radioactive contents of the package, or - on whether there are special arrangements governing the transport operation.


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Flow Diagram for Classification of RAM (non-Flow Diagram for Classification of RAM (non-fissile) into appropriate UN Number (1)fissile) into appropriate UN Number (1)

StartActivity ≤ AL or AC (236, Table 2)(1)(2) and;Non-radioactive solid objects contaminated on any surfaces ≤0.4 Bq/cm2 for beta and gamma and low toxicity alpha; or ≤0.04 Bq/cm2 for all other alpha emitters. (107f, 214).

Activity ≤ AL or AC (236, Table 2)(1)(2) and;Non-radioactive solid objects contaminated on any surfaces ≤0.4 Bq/cm2 for beta and gamma and low toxicity alpha; or ≤0.04 Bq/cm2 for all other alpha emitters. (107f, 214).

Exempt

N

N

Y

Y

(1) AL - activity limit for an exempt consignment in Table 2 of TS-R-1, 2009 Edition;AC - activity concentration for exempt material in Table 2 of TS-R-1, 2009 Edition;

(2) The number in ( ) – the paragraph number or table of TS-R-1, 2009 Edition;

(1) AL - activity limit for an exempt consignment in Table 2 of TS-R-1, 2009 Edition;AC - activity concentration for exempt material in Table 2 of TS-R-1, 2009 Edition;

(2) The number in ( ) – the paragraph number or table of TS-R-1, 2009 Edition;

49

Radioactive Material (107)(2)

(a) An integral part of the means of transport; (b) Moved within an establishment;(c) Implanted or incorporated into a person or live animal;(d) In consumer products;(e) Natural material and ores provided that the activity

concentration does not exceed 10 times AC.

Radioactive Material (107)(2)

(a) An integral part of the means of transport; (b) Moved within an establishment;(c) Implanted or incorporated into a person or live animal;(d) In consumer products;(e) Natural material and ores provided that the activity

concentration does not exceed 10 times AC.


END


50

UN 2911

UN 2909

Y

N

N

Y

N

YYEmpty

Packaging(425)

UN 2908

Manuf U/Th (426)(3)

Instruments or articles containing no more activity than the values: (423, Table 5)

Physical state of contents

Solids Liquids Gases

Special form

Other form

Tritium Special form

Other form

Item limits 10-2A1 10-2A2 10-3A2 2x10-2A2 10-3A1 10-3A2

Package limits A1 A2 10-1A2 2x10-1A2 10-2A1 10-2A2

N

UN 2910

N

Y

(3) Manuf U/Th – articles manufactured from natural uranium or depleted uranium or natural thorium;

(3) Manuf U/Th – articles manufactured from natural uranium or depleted uranium or natural thorium;

Material, other than instrument(s) or article(s), containing no more activity than the values: (424, Table 5)

Physical state of contents

Solids Liquids Gases

Special form

Other form

Tritium Special form

Other form

Package limits 10-3A1 10-3A2 10-4A2 2x10-2A2 10-3A1 10-3A2

Excepted packageExcepted package

Package surface dose rate ≤ 5 µSv/h (515)

Package surface dose rate ≤ 5 µSv/h (515)


END


51

UN 2913Y

N

Y

N

SCO(413)

LSA-I(409a)

Y

LSA-II(409b)

LSA-III(409c)

UN 2912

UN 3321Y

UN 3322Y

N

N

N

Industrial Package Type IP-1, IP-2, IP-3Industrial Package Type IP-1, IP-2, IP-3

The external radiation level at 3 m from the unshielded material or collection of objects≤ 10 mSv/h (516) and the total activity in a single hold or compartment of an inland watercraft, or in another conveyance does not exceed the limits (520,Table 7)

The external radiation level at 3 m from the unshielded material or collection of objects≤ 10 mSv/h (516) and the total activity in a single hold or compartment of an inland watercraft, or in another conveyance does not exceed the limits (520,Table 7)


END

Flow Diagram for Classification of RAM Flow Diagram for Classification of RAM (non-fissile) into appropriate UN Number (4)(non-fissile) into appropriate UN Number (4)

52

Type APackage

(427)UN 3332

NN

SpecialForm

NonSpecial Form

Y

Y

Type CPackage

(430, 434)

UN 2915

Y

N Y UN 3323Typ B

Package(430)

AirTransport Y

N

Activities not greater than the following (433)

(a) For LDRM — as authorized for the package design as specified in the certificate of approval,

(b) For special form radioactive material — 3000A1; or 100 000A2, whichever is the lower; or

(c) For all other radioactive material — 3000A2.

Activities not greater than the following (433)

(a) For LDRM — as authorized for the package design as specified in the certificate of approval,

(b) For special form radioactive material — 3000A1; or 100 000A2, whichever is the lower; or

(c) For all other radioactive material — 3000A2.


END


53

Special Arrangement (310)Radioactive Material for which classification into one of the above UN Numbers is impractical, may be transported, subject to competent authority approval.

Special Arrangement (310)Radioactive Material for which classification into one of the above UN Numbers is impractical, may be transported, subject to competent authority approval.

TypeB(U) PackageRequirements

(431)

UN 2916

N

Transportunder SpecialArrangement

UN 2917

Y

UN 2919

TypeB(M) PackageRequirements

(432)

Y

N

Transport prohibited but see Special Arrangement


END

Summary

• Based on the safety concept of the IAEA transport regulations safety in transport is mainly assured by the package itself together with some control measures during transport and approval needs by the competent authority, where necessary

• Optimal characterization of radioactive contents is an essential pre-requisite for optimal package selection

• Package selection should take into consideration not only material type, but also contents limits and shipment constraints

• By using the flow diagram for classification of radioactive material into appropriate UN number proper package selection can be supported


END

Questions?Questions?

55


END

Extra SlidesExtra Slides

56


END

IAEA Transport Regulations – Basis for safe IAEA Transport Regulations – Basis for safe transport, reviewed / revised continuouslytransport, reviewed / revised continuously

Oct. 2

009

Jun.

201

0

Aug. 2

010

Dec. 2

010

Apr. 2

011

Jun.

201

1

6th

Mar

ch 2

012

Start of the revision process(250 proposals from MS)

TRANSSC 19

TRANSSC 20

1st Draft of the new TS-R-1(to MS for comments, 120-Day-Role)

TRANSSC 21

2nd Draft of the new TS-R-1(send to MS)

TRANSSC 22(Adoption)

Board of Governors(Approval as SSR-6)

57


END

Implementation of IAEA Regulations through Implementation of IAEA Regulations through Dangerous Goods Transport Regulations Class 7Dangerous Goods Transport Regulations Class 7

58

international Recommen-

dations

international modal

provisions

national modal

provisions

IAEO UN

class 7

GGVSEBGGVSEBLuftVZOLuftVZO GGVSeeGGVSee

OTIF UNECE

all 9 classes of dangerous goods

ICAO IMOCCNR/UNECE


END

The Regulations apply to transport of radioactive material by all modes of transport

– on land (road, rail, inland waterway)

– on sea (maritime)

– In the air

Transport

comprises all operations and conditions associated with, and involved in, the movement of radioactive material; these include the design, manufacture, maintenance and repair of packaging, and the preparation, consigning, loading, carriage including in-transit storage, unloading and receipt at the final destination of loads of radioactive material and packages.

Radioactive materialis any material containing radionuclides where both the activity concentration (Bq/g) and the total activity in the consignment (Bq) exceed the values specified in Table 2 of SSR-6

Scope of the Transport Regulations


END

Scope of the Transport Regulations (cont.)

• SSR-6 does not apply to radioactive material:– that is an integral part of the means of transport– moved within an establishment not involving public roads or

railways– implanted in or incorporated into a person or live animal– In or on a person who is to be transported for medical

treatment– in consumer products having received regulatory approval,

following sale to the end user

• SSR-6 also does not apply to:– Natural material and ores containing natural radionuclides,

provided the activity concentration that does not exceed 10 times the values listed in Table 2

– Non radioactive solids objects with surface contamination levels ≤ levels defined in para 214


END

Objective and basic safety concept

The objective of these Regulations is to protect persons, property and the environment from the effects of radiation during the transport of radioactive material. This protection is achieved by requiring:

• containment of the radioactive contents• control of external radiation levels• prevention of criticality• prevention of damage caused by heat


END

Basic safety concept

These requirements are satisfied by

• applying a graded approach to performance standards applied to package designs contents limits for packages and conveyances

depending upon the hazard of the radioactive contents

• imposing requirements on design and operation of packages maintenance of packagings

considering the nature of the radioactive contents

• requiring administrative controls including, where appropriate, approval by a competent authority


END

Regulatory approach (SSR-6 para 106)

A graded approach is applied in specifying the performance standards which are characterized in terms of three general severity levels:

(a) Routine conditions of transport (incident free);

(b) Normal conditions of transport (minor mishaps);

(c) Accident conditions of transport.

In summary safety is mainly assured by the package itself together with some control measures during transport and approval needs by the competent authority, where necessary

Basic safety concept (cont.)


END

Type C package

• Needed only for very large quantities of radioactive material ( > 3000 A2 ) as approved by the CA for air transport

• Meets Type B(U) package design requirements + enhanced impact test (90 m/s on unyielding target), enhanced thermal test ( 800 °C for 1 h) and burial test to withstand air accident conditions of transport



• Subject to CA approval and package design approval certificate as Type C package issued by CA


END

Other PackageTypes

Packages containing fissile material (U-233,-235, Pu-239,-241), Type IF, AF, B(U)F, B(M)F, CF

Additional requirements regarding criticality safetySubject to CA approval (package design approval certificate)


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Other PackageTypes (cont.)

Packages containing Uranium Hexafluoride (UF6)

In quantities of 0,1 kg or more additional structural and integrity requirements regarding containmentSubject to CA approval (package design approval certificate H(U) or H(M))


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Introduction to Testing

• Type A and belowtesting programmes can be performed at many establishments

• Type B tests require more specialized, sophisticated & expensive equipment and facilities


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Type B Tests - Accident Conditions of Transport

Tests for Type B Packagesare designed to simulate extremely severe accidentsin surface transport modes


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Mechanical Tests for Type B Packages

Drop from 9m onto unyielding target

Para. 727

Drop from 1m onto flat top face of steel bar of 150 mm diameter mounted on unyielding surface


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Thermal Test for Type B Packages

Package fully engulfed in thermal environment providing a heat flux equivalent to flames of at least 800°C from liquid hydrocarbon pool fire, for at least 30 minutes -

– average flame emissivity > 0.9

– surface absorptivity = 0.8

Para. 728


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Immersion Test for Type B Packages

• Package immersed under 15 m head of water for 8h in attitude leading to maximum structural damage (test may be conducted on separate specimen)

• Enhanced water immersion test for packages containing more than 105 A2 under 200m head of water for not less than 1h

Paras. 729 and 730

regional training course on the safe transport of radioactive material in the caribbean module 2.4...

Documents