e YE i *' . INTERIM REPORT Accession No. ORNL/FTR-678 Contract Program or Project Title: Nuclear Safety Information Center Subject of this Document: Structural Mechanics in Reactor Technology Type of Document: Trip Report Author (s): Wm. B. Cottrell Date of Document: September 6, 1979 Responsible NRC Individual and NRC Office or Division: Dr. G. L. Bennett Office of Nuclear Regulatory Research Division of Reactor Safety Research This document was prepared primarily for preliminary or internal use. It has not received full review and approval. Since there may be substantive changes, this document should not be consid- ered final. Prepared for U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Under Interagency Agreements DOE 40-551-75 and 40-552-75 NRC FIN No. B0126 Oak Ridge National Laboratory Oak Ridge, Tennessee 37830 operated by Union Carbide Corporation for the Department of Energy INTERIM REPORT HC lesearcl anc "ec1nica IU33 i x Assistance Repor: ) y f u, yg . . OAK RIDGE NATIONAL LABORATORY OPERATED SV UNION CARBIDE CORPORATION NUCLEe AR Dm510N _ = = ,.. ORNL FOREIGN TMP REPORT ORNL/FTR-678 DATE: September 6, 1979 SUBJECT: Report of Foreign Travel of Wm. B. Cottrell, Manager, Safety Information Section, Engineering Technology Division To: Herman Postma F R OM: Wm. B. Cottrell PURPOSE: To attend the 5th Int ( national Conference on Structural Mechanics in Reactor Technology, August 13-17, 1979, and the following seminar on " Assuring Structural Integrity of Steel Reactor Pressure Vessels, August 20-21, 1979; to visit Dr. H. Steel of the GDR State Office for Atomic Safety and Radiation Protection. SITE VISITED: The above conference and seminar were held at the Inter- national Congress Center in West Berlin; the Wednesday, August 15th, meeting was at the GDR State Office for Atomic Safety ..nd Radiation Protection in East Berlin. ABSTRACT: Thomas A. Jaeger of the German (FRG) Bundesanstalt fGr Materialprtifung (BAM) originated and promoted the concept of an Internal Conference on Structural Mechanics in Re- actor Tect.nology which now has the support of over twenty companies, technical societies, and government organiza- tions in Europe, the United States, and Canada. The meet- ing in Berlin, August 13-17, was the 5th such biannual meeting and attracted some 1400 participants who could hear some 800 presentations in up to 15 parallel sessions. The main conference was preceded by one and followed by nine other seminars which were intended to provide a forum for in-depth discussions on topics of special in- terest. In addition to attending much of the conference and one post conference seminar, the traveler was invited by Dr. Jaeger to participate in the concluding press con- ference, and also had the opportunity to visit the GDR State Office for Atomic Safety and Radiation Protection. UC Research ant Technical w. Assistance Report . 'n f my I U ) ') . ] . . 1 Introduction The traveler, Wm. B. Cottrell, wae invited (on July 25th) by the Chairman (Dr. T. A. Jaeger) of the 4;n International Conference on Structural Mechanics in Reactor Technology to attend that conference and one of the following seminars at their expense (for plane fare and registration only). Inasmuch as the conference is both implicitly and explicitly concerned with reactor safety, I was pleased to be able to attend. In addition to the lain conference, August l}-17, I attended the following seminar on Assuring Structural Integrity of Steel Re- actor Pressure Vessels on August 20-21. I also had the opportunity on August 15 to visit Dr. H. Scheel of the GDR State Office for Atomic Safety and Radiation Protection. This memorandum is my report on these meetings and is divided into three sections (1) the 5th SMIRT Confer- ence, (2) the Seminar on Reactor Pressure Vessels, and (3) the visit to the GDR State Office followed by a summary statement concerning the SMIRT Conference. The 5th SMIRT Conference The first International Conference on Structural Mechanics in Re- actor Technology (SMIRT) was held in Berlin in 1971 and they have been held biannually since. The chief protagonist for this meeting was and is Dr. Thomas S. Jaeger of the FRG Bundesanstalt fur Fbterialsprufung (BAM) located in Berlin. However, the meeting has apparently filled such a need in the scientific community that over twenty companies, technical societies, and/or government agencies from Europe, the United States, and Canada participated in the organization and sponsorship of the 5th SMIRT Conference which was held in Berlin, August 13-17, 1979, (see Appendix 1). The SMIRT conferences are also unique in that each conference is preceded and/or followed by a number of seminar.c te rermit the in- depth discussion of special topics within the ss of SMIRT. The 5th SMIRT included ten such conferences; one of which Ts held on Thurs- day and Friday of the preceding week and the remai . der of which were held on Monday and Tuesday of the following week. The traveler attended the SMIRT Conference and cae of the follow- ing seminars at the special invitation of Dr. Jaeger who also arranged for the conference to provide the airplane fare and registration fees. Although I thus had no function at the meeting itself - although I was subsequently invited by Dr. Jaeger to participate in the concluding press conference on Friday, August 17th - the subject matter of the meeting was both directly and indirectly concerned with reactor safety As such, the meeting was directly concerned with my responsibilities both as Editor of Auclear Safety and as Director of the Nuclear Safety Information Center. In fact, it would appear that my invitation was prompted in the expectation that my presence would enhance the dis- sem nation of the meeting contents throughout the nuclear community. ' T . 2 - In order to provide some idea of the scope and contents of the meeting, the titles of all technical sessions are listed on Appendix 2 (total - 114 sessions). Each session averaged %7 papers (result- ing in something approaching 800 papers) and in view of this bulk, no attempt will be made to list all the papers here. However, a com- plete set of the proceedings is being mailed to the author and inter- ested persons may arrange to see my copy (when it arrives). The meeting was not unlike many others I have attended. In atten- dance (reportedly %1400) it was somewhat larger than the annual ANS meeting, but there were three times as many papers presented in some 10 tc 15 parallel sessions throughout the week, except for the plenary session on Monday morning, and this is the only session 1 will comment upon here. In addition to the customary formalities which involved R. K. Appleyard (Cammission of the European Communities), T. A. Jaeger (Conference General Chairman), W. LUder (Mayor of Berlin) and B. A. Boley (Deputy General Chairman), the plenary session consisted of three formal presentations as follows: 1. Guido Brunner (Member of the Commission of the European Communities) " Situation and Perspectives of the Energy Policy in the European Community" 2. Mike McCormack (Member of Congress of the United States of America) " Energy Policy of the United States in the International Community" 3. Peter For'escue (Technical Director, General Atomic Company, San Diego, California "Long Term Nuclear Energy Strategies: The Role of Fission and Fusion" All three are nuclear advocates, however, Brunner's talk was more historically oriented, expressed the need for environmental protection as well as meeting the energy needs of society in which both coal and nuclear are needed. McCormack's talk constituted a solid endorsement of nuclear power based upon his assessment of the energy situation and the available alternatives. Fortescue's talk was another in his con- tinuing attempts to gain support for gas-cooled reactors and/or the thorium fuel cycle. (I have a copy of the complete text of each of these three papers.) Assuring the Structural Integrity of Steel Reactor Pressure Vessels The two-day seminar on this topic was one of ten such reminars that were held during the week either preceding or following the SMIRT Conference itself. The list of all such conferences is pre- sented in Appendix 3. The agenda for the Pressure Vessel seminar is shown in Appendix 4. All of these seminars are on topics within the technical scope of the SMIRT Conference in which the program sponsors o,, ' . . 3 felt that there was a need for additional meetings on specific topics. Each such seminar is conducted in a " workshop" atmosphere for the pur- pose of providing a forum for extensive in-depth discussions. For persons interested in more detail on this seminar, I have a copy of the preprints which includes many but not all of the papers presented. The session was " enlivened" by a review of the Three Mile Island Accident by Dudley Thompson, Deputy Director of the NRC Division of Inspection and Enforcement (substituting for Vic Stetto). This presentation was not included in the preprints, but was based upon the NRC report (NUREG-0600) " Investigation Into the March 28, 1979, Three Mile Island Accident by Office of Inspection and Enforcement" which had been released a few weeks earlier. GDR Office for Atomic Safety and Radiation Protaction On August 15th this traveler, together with Betty Maskewitz (Director of the Radiation Shielding Information Center, ORNL), visited Dr. H. Scheel of the GDR State Office for Atomic Safety and Radiation Protection in East Berlin. The visit was an experience which provided little, if anything, of technical value to me pertaining to nuclear safety, but which did provide me with a wealth of insight as to the role and status of East German science. In addition to Scheel, Maskewitz and myself, we were joined in midmorning by Dr. Wandt, a nuclear physicist from the DDR Academy of Science in Dresder.. Both Scheel and Wandt had some awareness of U.S. technology through information made available through IAEA in general, and INES in particular, but virtually no other contact (except with RSIC). East Germany has a 70 MW reactor at Rheinsburg now used pri- marily for training purposes, has two 440 MW(e) nuclear plants on the Baltic (Machteburg area) and is building a third. These are USSR de- signed PWR plants which are built by the East Germans with Russian supervision. However, the Russians perform all the physics and safety calculation which the East Germans do not check. The principle func- tion of the State Office was for the training of nuclear industry personnel in radiation safety. However, we saw no facilities nor did we meet any other GDR personnel aside from the two identified above. It appears f.e me tha t the East Germans are interested in finding out what's going on in the rest of the world, but that they are so sup- pressed by the communistic autocracy that they don't dare to take much initiative. IO?7 8UJJ . . 4 . Summary Statement (Note: I prepared the following statement in anticipation of using same at the press conference on Friday, August 17, to which Jaeger had invited me. However, in view of linguistic difficulties at the press conference, Jaeger did most of the talking and I responded only through him to a few direct questions (in German). However, the following statement is as appropriate for this report as it would have been for the press conference.] It would not be possible to get so many people, many of whom came great distances, if SMIRT did not have real advantages to offer in their work. True, a lot of good work goes on in the United States and it would certainly be possible for us to have a meaningful meet- ing on just the U.S. work - but it is equally true that there is a lot of good work going on in the rest of the world (Germany, France, United Kingdom, and Japan, to mention but a few places) and it is mutually advantageous for the scientific community to share the re- sults of such research which are directed to the welfare of all mankind. I first met Thomas Jaeger over ten years ago in the United States when the concept of these SMIRT Conferences was a vision he was striv- ing to realize. At that time I had no way of knowing how spectacularly successful SMIRT would become under Jaeger's guiding hand. Given the magnitude of the many research programs relating to structural mechanics as applied to reactor technology, a SMIRT-type conference may have been inevitable. But whether or not SMIRT ceuld have existed without him, there is no doubt that Thomas Taeger was the right man, at the right place at the right time. The first SMIRT Conference (in 1971) and all subsequent SMIRT Conferences have been indelibly stamped with his genius -- as is amply attested by what all of us have experienced here this week. If I could digress a bit, I would like to attempt to place the significance of this conference in some broader context. Civilized man noeds energy - not only to maintain his standard of living and to raise the standards of those less fortunate, but also to improve the standards of all. Energy comes from many sources and assumes many forms: the use e' energy for the generation of electricity is a role that nuclear power seeks to fulfill -- and nuclear power can provide electricity; less expensively, more safely, and with less environmental impact than any other energy source currently avail- able to mankind for the large scale generation of electricity. The barriers to the greater exploitation of nuclear power are not technical; in the United States at least they are educational, societal, and in the final analysis - political. But that's another atory - let me return to the importance of SMIRT. ~ : ' . \o35 n) . 5 It is possible for me to cot. elude that nuclear power is safe, in large part, because of the type work which was presented here this week, and which will continue in even more excruciating detail in cer- tain areas next week. Nuclear safety - as opposed to structural mechanics - is an inte- grated science (some might say art), but one cornerstone of nuclear safety is the structural integrity of the reactor system -- and that's what SMIRT is all about. This cornerstone has become well established. Nuclear reactors were being safely built and operated without SMIRT, but they certainly are being more safely - and more economically - built with SMIRT and in a more precisely determined manner. All users of electricity, in general, and we in the nuclear com- munity, in particular, owe Tom Jaeger a debt of gratitude for his contribution to the safe development of nuclear energy. Thank you for this opportunity to express myself on these matters of such im- portance to the welfare of mankind. G, ? i DP%D 7 L b O APPENDIX 1 [D ) h r] r\t } , jq i;c( Q J E b. I.)AJ [TO _JJ 5th INTERNATIONAL CONFERENCE ON SMIRT (Sponsors and Executive Committee) k PATRONAGE EXECUTIVE COMMITTEE The 5th SMiRT Conference and its associated Pre- and Post- Thomas A. JAEGER, General Chairman. Scientshc Chairman Conference Seminars will be held under the patrortage of and Organization Chairman Direktor und Professor. Bundesestait fur Mater aiprutung Dr. Guido BRUNNER o_1000 e,,i,n (west) as. Germany Member of the Commission of the European Communities Bruno A. BOLEY, Scientibc Chairman and Deputy General Chairman Dean. Tne Technoiogicalinstitute. Northwesiern Un.versity CONFERENCE ORGANISATION BY: Evansion. m.no,s so2ci. u s A Raymond K. APPLEYARD. C E.C. Representative International Association for Structural Mechanics o, rector Generai D4ccioravecenerai sc,ent t.c and Tecnn.canntormat.on in Reactor Technology e. V., and and information uanagemeni iD o xiiii Cenumn or ine European Cornmun.t,n erusseis seig,um Commission of the European Communities, Brussels F. CA CCIA-DOMINIONI. C.E.C. Representative Bundesanstalt fur Materialpru.. fung (BAM), Berl.in Drector Researen. Dreiopmeni and uuci,a, pouc, o,,,c,o,a,e United States Nuclear Regulatory Commission, U"''' a''ai Anearen. science and Education :a a xii) Cmamn'*'''G'e the E canur Comrnu n,i.n Brum's se,u rn Washington, D.C. John M. GIBB. Secretary of Executive Committee Head Department for Dissemination or Research Resuits Lusembourg in cooperation with: Drectorate.Generai sc ent,fic and Technicas inr ormai.on and intermation Bechtel Power Corp., San Francisco /Los Angeles. Cal . U.S A. Management (D G xm> Electric Power Research Institute (EPRI). Palo Alto. Cal., U S.A. Commiss.on of the European Communities Brusseis Belg um Franklin ResearCh Center (FRCL Philadelphia. Pa., U.S A. Robert AVERY Massachusetts Institut3 of Technology (MIT). Carnbndge. U.SA. D' recto'. Reactor Ana!yses and saiety Devesson Northwestern University. Evanston. Ilknois. U S A. ^'9 ""' Na'onal Laboratory Argonne liiinois 60439 'I s A MacNeal-Schwenci:er Corporation. Los Angeles. Cat , U.S A. Franklin E. COFFMAN Associated Nuclear Services. Epsom. Surrey. United Kingdom ^ ''nq Oirector. Div,s,on of Deveinement and T-chnoiogy. ottce of Fusion Energy. United states Department of Energy Washing'on D C 20545 U s A Lawrence C. SWO. U.S N R C. Representatn 9 Daector Division of . . actor sa'ety Aesearch United state. Nuciear Aegulatory Commission Wasnington D C 20555 U s A Jean RASTOIN SMsRT-6 General Chairman CO-SPONSORING INSTITUTIONS AND SOCIL' ?S Cret Departernent oes ciuon uecan.ooes ei rne,,,, ,s Commissariat a i Energ ; 1033 - / - 8 APPENDIX 2 [s, ![> h., 'ini [) y ;" or,! . j . n ,,!"ri A l.t SMIRT-5 SCIENTIFIC PROGRAM rd '! >s!.!i h Ub y!:iU n.j C J TOPICAL GROUPING OF THE CONFERENCE SESSIONS Thermal and Fluid / Structure Dynamics Analysis Division B. Division F. Structural Analysis of Reactor Core and Coolant B 1. Computational Methods | Circuit Structures B 2. Computational Methods 11 F 1. B 3. Computational Methods ill Reactor Core Structures F 2. Special Problems B 4. Acoustic Methods F 3. Piping: Structural Analysis B 5. Flow Induced Vibrations F 4. Piping: Dynamic Analysis B 6. PWR Problems B 7. BWR Problems 1 F 5. Fracture Mechanics F 6. Pipe Rupture B 8. BWR Problems 11 F 7. Pipe Rupture: Methodology Division C. Analysis of Reactor Fuel and Cladding Materials F 8. Components and Support Systems F 9. Heat Exchangers CI. IFuel and Fission Product Behavior 1 C aht F els Analy s mvision G. StrucW Analysis of hl hacW Wem C3.i Cladding Matenals Behavior i Vessels C 3 g. Cladding Matenals Behavior il C 4g. Failure Cntena i G 1. Overviews of Integnty Assessment G 2. Fracture Toughness Measurements C 4||. Failure Cntena il G 3. Fracture Mechanics: Elasto-Plastic Division D. Structural Analysis of G 4. Fracture Mechanics: Special Aspects Reactor Fuel Elements and Assemblies G 5. Fracture Mechanics: Stable Crack Growth G 6. Fracture Mechanics: Matenals Modeling D 1. Fuel Performmce Analysis G 7. Fracture Mechanics: Computation D 2. Pellet-Clad Interaction Effects on Clad Behavior G 8. Fatigue D3 Methods for Analysis for Pelle'.Olad Interaction G 9. Fracture Mechanics: Thermal Effects D 4. Thermal Reactor Subassembly Analysis G 10. Stress Analysis D5 Fast Reactor Subassembly Analysis D6 Accident and Overpower Transient Analysis of Division H. Structural Engineering of Prestressed Thermal Reactors Reactor Pressure Vessels D 7. Accident and Overpower Transient Analysis of Fast Reactors H 1. Matenals Behavior i H 2. Matenals Behavior || Division E. Energetics and Structural Dynamics in Fast H 3. Desian. Research and Surveillance of PCVs Reactor Accident Analysis H 4. Structural Analysis of PCVs and Components H 5. Liner and Thermal Barner Systems E 1. HCDA Containment H 6. Concept and Research for a PCV E 2. Upper Core Structures and Coper Response with Hot Liner E 3. Coolant Systems and Matenals Response H 7. Concept and Research for a PCIV E4 Expenments and Code Venfication i H 8. Concept and Research for a PCV for the LMFBR E 5. Expenments and Code Venfication || E 6. Core Components Response o 1033 m . !: ' ~ 10]''' APPENDIX 2 (cont'd) [ iJ|1 G ~'d, (*0 i fl' [ n] '( ';U 1 p f. , y d(i m ( [ L| g b Division J. Loading Conditions and Methods for Structuisl Analysis Structural Analysis of Reactor Containment Division M. integraM Memods of hetural Analysis J 1. General Design Cntena and Containment Seldon M 2. Numencal implementation of inelastic Matenal Des n and Simplified Methods of Analysis oncr nan n esign and Analysis M 3. oP " J 4. Concrete Containment: Testing Behavior as J 5. Design and Analysis of Slabs and Structures Computational Techniques for Plate and Shell J 6. Structural and Leak Testing M 5. and Design of Containment Components J 7. Impact Load Analysis and Design 1 M 6. C p ational Techniques within Finite Eter ent J8 pact ad Analysis and Desian 11 M 7. Co p ational Techniques within Finite Element J 10. Impulsive Load Analysis and Design M 8. o at la tic Methods in Structural Analysis Division K. Seismic Response Analysis of Nuclear Power M 9. Numerical Procedures for Fracture Mechanics Plant Systems M 10. Dynamic Modeling in Seismic Analysis M 11, Advances in Linear Boundary and Initial Value K 1. Ground Motion Problems K 2. Risk Analysis i K3 Risk Analysis || Division N. Thermat, Materials Engineering, and Structural K 4. Design Concepts f4echanics Problems of Future Fusion Reactor K 5. Soil-Structure interacton Power Plants K 6. Soil-Structure interacton || K 7. Underground Structures K loor Re pon Analys s art 1. Engineering Concepts and Thermo. Fluid- K 10. Response of Piping and Equipment I Dynamics of Future Fusion Reactor Power Plants K 11. Response of Piping and Equipment || N 1.1 Engineenng Concepts of Magnetic Confinement K12. Reactor Core and Fluid Related Structures i Fus:on Reactor Systems K12n. Reactor Core and Fluid Related Structures 11 N 1.2 Engineenng Concepts of inertial Confinement and K13i. Dynamic Testing and Quahfication i Hybnd Fusion Reactor Systems and Safety K13n. Dynamic Testing and Qualification || Considerations N 1.3 Thermal-Fluid Dynamics of Fusion Power Reactor Panel Session Systems JK-P Status of Research in Structural and Mechanical Engineenng for Nuclea Power Plants art 2. Structural Mechanics Problems of Fusion Power ** Division L. Materials Modeling and inelastic Analysis of MetalStructures N 2.1 Structural Analysis of Magnets N 2.2 Magnet Technology L 1. Advanced Theones 1 N 2.3 First Wall Performance in Fusion Reactors L 2. Advanced Theones || N 2.4 Fusion Blanket Structural Analysis N 2.5 Matenals and Plasma-Fluid Wall Interaction ff , |, L5 Fracture. Rupture L 6. Codes and Cntena L 7. Matenals Behavior L8 Apphcatons i L9 Apphcatons il L 10 Simphfied Methods L 11. Damage L 12. Expenments 1 L 13. Expenments || t L33 mi . 10 APPENDIX 3 PRE- AND POST CONFERENCE SEMINARS The following SM RT 5 pre * and post-conference seminars will be conducted in a workshop atmosphere,for the purpose of providing a forum for extensive endepth discussions on special SMiRT topics: Mathematical / Mechanical Modeling of Reactr,r Fuel Elements Fracture Resistance of Reactor Components Fluid-Structure Interaction Analysis in LWR Systems Tontainment of Fast Breeder Reactors Assuring Structurallntegrity of Steel Reactor Pressure Vessels NDE in Relation to StructuralIntegrity Extreme Load Design of Nuclear Power Plant Facilities inelastic Analysis and Life Prediction in High Temperature En- vironment Structural Reliability of Mechanical Components and Sub- assemblies of Nuclear Power Plants Computational Aspects of the Finite Element Method . 7? 1IU f) J J vm . . 11 h hb if ' h ! j p' $ APPENDIX 4 U ''?' I {, nq7 p( g ; ' . 'h]lp !:.I. ~l;ji.!! o i'i L & L E 7 1st International Seminar on: PROGttAM ASSURING STRUCTURAL INTEGRITY Aueust25.1979 "'" 0F STEEL REACTOR PRESSURE VESSELS @iM SESS Es"6,$ie,''aC'Z"Ication"" A,,ects o, held in conjunction with the StructuralIntegrity Assurance 5th International Conference on Session Chairman L E Steele. USNAL. O S A. STRUCTURAL MECHANICS IN REACTOR TECHNOLOGY A R. Ruf, Kraftwerk Umon. Fed. Rep Germany Principal Speaker on Design and Fabncation Place: International Congress Center Berlin (ICC), Berlin (West) B. R.B. Cambian. Westinghouse-Nuclear. Belgium Date. August 20-21,1979 e Registration Fee: DM 200 *) Optimized Reactor Vessel of Forged Pieces C. Z N Ibrahim. Sargent & Lundy U S A Seminar Co Chairmen: Confidence and C iservatism of Dynamic Responses Dr Karl E. Stahlkopf Mr. Lendell E. Steele a G Batholome. Kraftwerk Union. Fed. Rep Germany Program Manager Head. Thermostructur al Materials Branch Methodsg for t Evalution of the Reliability of Pnmary Dectnc Power Research Inst 4tute and Associare Suoennfende"'- 34f2 H4.e* A,e. Bor 1o472 MarenalSc,ence & Technosogy D+sion. E. J G Blauel. T. HoHstein. M Wenk. IFKM. F A G Pa r o A'to. CA 94303 U S A Naeat Research Laboratory p, oEvaluation p_ treland. of ETl Fracture U S A~ Mechanics Materials Parameters Washmgro n. O C 20375. U S A Relative importance of Dynamic Fracture Toughness Seminar Sponsors: International Association for SMiRT, e.V. G B. Houssin. P. Moulin, G Slama. Framatome. France Commission of the European Communities ",9 S'"S''*'ty of Welds of Nuclear Reactor United States Nuclear Regulatory Commission S'$" The Metal Properties Council, U.SA H. W P. Tiler, R W. Hill. Westinghouse Nuclear International' The Electric Power Research Institute, U.SA Belgium. Developments in the Use of Lage Forgings for Reactor Vessel Construction Bundesministerium fur Forschung und Technologie H M7 n-Service Degradation and provisions to Organizational Support: Bundesanstalt fur Matenalprufung (BAM), SESS,_ O,N ICC, Dept. of Organeation and Operation Session Chairman Karl E. Stahlkopf. EPRI. U S A. A. A D Rossin. Com Ed. U S A Generat informaton Pnncipal Speakter on Operational Aspects The program of the Seminar consists of four sessions and will be conducted in a worb B. P. Hutton. Battelle-Pacific. U S A shop atmosphere Each session a to be opened by a pnncipal iactu re tonowed Dy short Acoustic Emission as a Measure of VesselIntegrity presentations by speciansts The mam emphasis. however. is on d,scussion and mutual C. K. Fox, R B HtII. SSEGB. U K. exchange of information For this reases the participation rs limited to 120 The conter- Probabilistic Assessment of Defects Dunng Service ence ranguage * fr be Engt sh Prepnnts will te provided at the meet nq Proceedings D. L R. Harrop. UKAEA. U K *iti ee publisned in a hard bound volume by APPUED SCIENCE PUBU$HERs. LTD Modehng in-Service ins t Additional mquiries may be add'essed to the Seminar Chairmen E. G R Odette. UCSB U S A Predicting in-Service Irradiation seepe F C l L Evans T R. Mager. Westinghouse, U S A This conference is intended to review all tactors which might affect structurat integnty irradia n Embrittlement of Reactor Vessels Operating of stees reac tor pressure vesses Topics witi cowr tne design. matenais seection. fabncation poss bie problems of m-service degradation and provisions for meetmg G S Yanich.ko. Westinghouse. U S A these as *esi as the national codes standards and regu$ations which irepmge upon the Saturation Effects design construction. and operation of nuclear power plants as these may affect the August 22,1979 pnmary reactor vesses those made of steel 8 30.-12 00 SESSION til- Codes, Standards, and Regulatory Aspects Based on over twenty years of e*penence fee evolutionary growth of the science and of Structuralintegrity technology of the subiects cited permits a tuil drussion of the factors which. at eacn staoe of a reactor vesses s hte. rray mfluence its structurai mtegnty it is intended mat the Session Chairman L E. Steele. NRL. U S A discussion will cover especially potential degradation m construction and service as A. PnncipalV F. Stello. Speaker USNRC. on Regul U S A ,3 tory Aspects weit as the steps now bemg taen to minimas chances for taisure of a steen nu cica' B. J Pernn, BMI. U S A pressure vessel A panel descusseon draning together esperts from the vanous subiect areas treated wist Contnbution of ASTM Standards decis on design and fabncation technoiogy. as weil as e penence m the operat.on of C A L Lowe. Jr . B & W. U S A. nuclear power piant and how tsese together permit one to proiect the potential for Surveinance Programs to Insure Continued Licensability structural rehabihry in addition. the recent accidens m the USA will resuit in a focus on D W Schmitt. Kraftwerk Union. Fed Rep Germany Detelmening the influence of Quahty Assurance on Rehabil t factors which may enng further pressure to bear on the worto s codes and regularons i E. W L Server. R O R,tchie. R A. Wulfaert* Fracture Control' which govern the construction and operation of nuclear power piants Our emphasis USA was de on the pnmary pressure boundary Tegn 6 @mq weg gw%m otnective 13 30- SESSION IV: Panel Discussion Panel Moderator: K E. Stahikopf. EPRI. U S A. The pnmary ociective of the conserence is in deveiop a womshop m which the pnncipai panelists speamers. the mvited spokesman. and the autnors of contnbuted papers mieract with Hu n Bat le Pacific Northwest. U S A the audience en a tutt scale discussion of the entical aspects of stees reactor pressure . .UK vesses integnty A D Rossen. Com Ed. U S A R Auf. Kraftwerk Union. Fed Rep Germany *hrore Val d only for pre-regrstrarron ne brer ,Iune30. 1979 therearter rae reg stratron C Z Serpan. Jr . USNRC. U.S A tee ,s DM 300.- L E. Steele. USNRL. U S A V. SteHo. USNRC. U.S A ~ | 3 9 l , ) .# . b 13 DISTRIBUTION 1-2. Assistant Administrator for International Affairs, DOE, Washington 3. Director, Office of Nuclear Regulatory Research, NRC, Washington 4. Director, Division of Reactor Safety Research, NRC 5. Assistant Director, DRS for Water Reactor Safety Research, NRC 6-8. Director, Division of Reactor Licensing, NRC, Washington 9-10. Office of Standards Development, NRC, Washington 11-15. Executive Secretary, Advisory Ccmmittee on Reactor Safeguards, NRC, Washington 16. G. L. Bennett, Chief, Research Support Branch, NRC/RES 17. Director, Division of Safeguards and Security, DOE, Washington 18-19. Director, Division of International Security Affairs, DOE, Washington 20-21. Director of International Programs, NRC, Washington 22-23. Division of Technical Information and Document Control, NRC, Washington 24-25. Technical Information Center, Oak Ridge 26. J. A. Lenhard, DOE /0RO 27. W. T. Sergeant, DOE /0RO 28. R. F. Hibbs 29. Herman Postma 30. J. R. Buchanan 31-35. Wm. B. Cottrell 36. M. H. Fontana 37. H. W. Hoffman 38. J. E. Jones 39. R. E. FbcPherson 40. B. F. Mastewitz 41. F. R. Mynatt 42. I. Spiewak 43. H. E. Tramr. ell 44. D. B. Trauger 45. G. D. Whitman 46-47. Laboratory Records Department 48. Laboratory Records Department (RC) 49. Laboratory Protection Division 50. ORNL Patent Office " 51. ORNL Public Relations Office 1033 .'