"Heavy-Section Steel Technology Program," foreign trip rept.ORNL/FTR-1079
Contract Program or Project Title: Heavy-Section Steel Technology Program
. Subject of this Document: Report of Foreign Travel of G. D. Whitman, Program Manager, and R. D. Cheverten and J. G. Merkle, Task Leaders, Engineering Technology Division
Type of Document: ORNL Foreign Trip Report
Authors: G. D. Whitman, R. D. Cheverton and J. G. Merkle
Date of Document: June 5, 1981
Responsible NRC Individuhl and NRC Office or Division: M. Vagins, Division of Engineering
Technology, NRC - FTS 443- %03
This document was prepared primarily for preliminary or internal use. It has not received full review and approval. Since there may be substantive chaages, this document should not be con- sidered final.
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Washington, DC 20555 Under Interagency Agreements DOE 40-551-75 and 40-552-75
NRC FIN No. B0119
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04Tci June 5, 1981
SUBJEC;, Report of Foreign Travel of G. D. Whitman, HSST Program Manager, and R. D. Cheverton and J. G. Merkle, Task Leaders, ETD
T o, Heman Postma
FRou: G. D. Whitman, R. D. Cheverton and J. G. Merkle
PURPOSE: To review and plan additional research and development under the USNRC/BMFT Cooperative Program in LWR primary system integrity as performed at ORNL and MPA
SITE VISITE~ May 21 and 22, 1981 Staatliche MaterialprUfungsanstalt (MPA) Stuttgart, Germany Dr. K. Kussmaul
ABSTRACT
The travelers, with a representative of the USNRC, attended a two-day meet- ing at Staatliche MaterialprUfungsanstalt (MPA), Stuttgart, Germany, under the cooperative agreemr.nt between USNRC and the Federal Ministry of Research and Technology (BMFT) to review projects sponsored by each organization, to review cooperative projects and to plan new cooperative work under the agreement.
Projects in fracture mechanics, intermediate size and large vessel testine, themal shock and irradiation were reviewed. New cooperative work was planned on the analysis of experiments on pressurized thermal shock, thermal shock, and nozzle corner flaw behavior. The feasibility of performing a large compact specimen crack arrest test will be studied,and future ex- changes for cooperative planning on the HDR pressurized thermal shock experiment were discussed.
NRC Researcl anc ecanica ~
ERC Research ancTechnical\ SS S anCe 3ep0TtINTRODUCTION
The travelers, G..D. Whitman, R. D. Cheverton and J. G. Merkle, in the '
company of M. Vagins of the NRC, attended a two-day meeting with repre- ; sentatives of MPA-Stuttgart to review subjects on LWR primary system
integrity research and development which were of common interest under the cooperative agreement between NRC and BMFT. Major emphasis was placed or, reactor riressure vessel materials and fracture analysis which are the areas of primary interest in Heavy-Section Steel Technology (HSST) research and hvelopment.
The meeting was organized around a few presentations on specific subj. cts followed by general discussions. An agenda was available as shown in Appendix D; however, not all of these items were covered in detail nor in the order listed. Tn.nics that were formally addressed included general introductions and organizational structure, fracture mechanics, vessel testing and thermal shock including pressurized thermal shock. A tour was made of MPA facilities, and a courtesy call was made on Professor Argyris on the afternoon of the second day. The itinerary of the travelers is shown in Appendix A, and a list of participants is shown in Appendix B.
MEETING TOPICS
Professor Karl Kussmaul, Director of the MPA, attended all discussions and i opened the meeting with an overview of their work to include a statement
that component safety is budgeted at $250M DM for a five-year period. There are thirty cooperative institutions participating directly or through subcontracts with the principals. The integrity of components is organized around sixteen projects which are supported by funds supplied equally from the government and industry. There are activities involving full-scale components. One of these is the Superheated Steam Reactor (HDR) at Grosswelzheim, which is being used for several projects culminating in simulated faulted condition tests on the pressure vessel. Another is a 900 MW(e) BWR pressure vessel which is erected at f1PA for nondestructive testing development. Kussmaul described plans to expand their computing facilities at MPA to include a new building housing a UNIVAC 1100/61 machine and auxiliary processing.
Milton Vagins described the organization of the NRC, goals, budgets and current interests in pressurized thermal shock.
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detected with high reliability. _Issler presented a correlation developed by MPA between upper shelf Charpy impact energy and tensile reduction of area. He then discussed net section collapse criteria, concluding that 100J upper shelf Charpy energy ard 55 percent reduction in area must be achieved to eliminate fracture-governed failur .
Dietmar Sturm of MPA reviewed the vessel tests-that have been performed to develop data to establish leak before break criteria in piping systems. This is an extensive empirical program from which rules will be developed to determine critical flaw orientations and sizes in cylindrical sections under PWR and BWR cocditions. These tests are producing-a great deal of data and could be of interest to us in developing crack arrest behavior. They are, however, being performed with relatively thin wall sections and machined notches instead of fatigue-sharpened cracks which may detract from their usefulness in our work. This project is not unlike work per- formed at Battelle Columbus Laboratories several years ago.
Overcooling accidents with and without internal pressure including nozzle corner flaws were extensively discussed. J. Jansky described MPA work on nozzle corner flaw cracking by thermal fatigue including plans for nozzle corner cracking in the HDR vessel. Cracks have been produced in nozzle corner regions of expoeimental pressure vessels by local thermal cycling combined with constant internal pressure. The internal shape of the noz- zie to cylinder intersection region changed in a ratchetting manner, and the ASME Section III fatigue design curve was found to fit the fatigue'
crack initiation data for these tests. Jansky also described a series of pressurized thermal shock experiments to be performed on hollow cylinders in a large tensile testing machine to simulate pressure loads.
R. D'. Cheverton presented HSST work on thermal shock and overcooling acci- dent analysis. de reviewed the capabilities of the computer code OCA-I and described typical results. This work was of considerable interest to.
MPA personnel, and several spirited discussions ensued on lower bound;-
toughness concepts, conservatisms in the pressurized thermal shek anal- yses, materials simulation techniques and failure experience from thermal cycling. The utilization of electroslag welding and weld-deposited mate-'
! rials with variable chemistry to simulate low toughness and variable tough- ! ness was introduced by Kussmaul, and a report on the weld deposit fabri-
cation technique was given to us for reference. G. D. Whitman briefly described the planned HSST pressurized thermal shock experiment usingL
| intermediate vessels.
We toured the MPA facilities at the end of the first day. This institute is well equipped to perfonn tests on large-scale specimens. In particular,
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well equipped machine shops where sawing, cutting, shaping, turning and boring operations can be performed for specimen blanking and fabrication and test component construction.
SUMMARY OF AGREEMENTS
Agreements for future work included the following:
Item la: ORNL will carry out a full pretest fracture analysis of the first MPA pressurized thermal shock test.
Item Ib: MPA will supply ORNL with complete experimental design param- eters including material properties, pressure-temperature time function of coolant ar.d external loading. (MPA will supply ORNL with a specimen temperatura vs time plot.)
Item 2a: MPA will carry out a full fracture analysis of TSE-5A.
Item 2b: ORNL will supply all necessary data on TSE-5A.
Item 3: ORNL will carry out a stress intensity (factor) determination for the naturally grown flaw in the nozzle corner of the MPA model vessel test.
Item 4: MPA and ORNL will study the possibility of performing a large (20 in.) CT-K test using side wedge loading.la
Dr. Kussmaul gave G. D. Whitman the transmittal letter and data compila- tion for the specimens that MPA shipped to ORNL. These specimens will be used 11 the fourth capsule of the current HSST irradiation series as part of the cooperative program.
SUMMARY AND EVALUATION
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The work we have under way in cooperative irradiation effects is progress- ing satisfactorily, and it has been designed to enhance our data base by the inclusion of lower toughness materials.
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ITINERARY
Travelers: R. D. Cheverton, J. G. Merkle and G. D. Whitman
Knoxville to Stuttgart, GermanyMay 19-20 Travel -
May .'l-22 Meetings - MPA, Stuttgart, Germany
May 23 Travel - Stuttgart, Germany to Knoxville
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J. Fbbl MPA
D. Sturm MPA
R. D. Cheverton ORNL
J. G. Merkle ORNL
G. D. Whitman ORNL
H. Schuls GRS (Society for Safety) M. Vagins USNRC
J. Jansky MPA
5. MPA-Seminar, Safety and Testing - Conception for Components and Primary Systems, Staatliche MaterialprUfungsanstalt, Universitst Stuttgart., 11/12 Octoba- 1979.
6. MPA-Seminar, Fractu.e Concepts and Nondestructive Examination, Staatliche MaterialprUfungsanstalt, Universitht Stuttgart 9/10 October 1980.
MPA Stuttgart, "New Testing Facilities," 1980.
MPA Stuttgart, "100 MN Tensile Testing Rig."
H. Jansky et al., "HDR-Thermal-Shock-Programme Results from Investigations of Plates and Model Vessels (Preliminary Experiments on HDR-Pressure Ves- sel)," HDR-Safety Programe, 3rd Status Report, 4 December 1979, Staatliche MaterialprUfungsanstalt, Universitst Stuttgart.
H. Jansky et al., "HDR-Tnermal Shock Programme Results from Model Vessel (Preliminary Experiments on riDR-Pressure Vessel)," HDR-Safety Programme, 4th Status Report, December 1980, Staatliche MaterialprUfungsanstalt, Universitat Stuttgart.
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Exchange of information between
- Radiation program J. F6hl - Intermediate size and large D. Sturm
vessel testing - ZB1 R. Gillot -17 MoV 84
- HDR J. Jansky
DISTRIBUTION
1-2. Assistant Secretary for International Affairs, DOE, Washington, DC 3. G. Arlotto, Director, Division of Engineering Technology, NRC,
Washington, DC 4. Director, Office of Nuclear Regulatory Research, NRC, Washington, DC 5. Director, Division of Safeguards and Security, DOE, Washington, DL
6-7. Director, Division of International Security Affairs, DDE, Washington, DC
8-9. Director, International Programs, NRC, Washington, DC .
10-12. Director, Division of Reactor Licensing, NRC, Washington, DC 13-14. Office of Standards Development, NRC, Washington, DC;
15-19. Executive Secretary, Advisory Committee on Reactor Safeguards, NRC, Washington, DC
20. L. S. Tong, Chief Scientist, Office of Nuclear Regulatory Research, NRC, Washington, DC
21. C. Z. Serpan, Division of Engineering Technology, NRC, Washington, DC
22. M. Vagins, Division of Engineering Technology, NRC, Washington, DC ,
23. J. A. Lenhard, DOE /0R0 24. J. S. Denton, DOE /0R0 25. Herman Postma, Director, ORNL 26. S. E. Bolt 27. R. H. Bryan 28. J. W. Bryson 29. R. D. Cheverton
| 30. J. R. Dougan 31. P. P. Holz 32. C. C. Hopkins 33. A. L. Lotts 34. J. G. Merkle 35. R. K. Nanstad 36. G. C. Robinson 37. J. E. Smith
i 38. H. E. Trammell 39. D. B. Trauger
; 40. G. D. Whitman 41-42. Laboratory Records Department
43. Laboratory Records Department - RC 44. Laboratory Protection Division 45. ORNL Patent Office'
46. ORNL Public Relations Office-
47-48. Division of Technical Information and Document Control, NRC, Washington, DC
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