_STP_1513-2010.pdf

www.astm.orgISBN:978-0-8031-5523-7Stock#:STP1513JAI Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle:24th VolumeSTP 1513Busby|HansonJournal of ASTM InternationalSelected Technical Papers STP 1513Effects of Radiation on Nuclear Materials and the Nuclear Fuel Cycle24th VolumeGuest EditorsJeremy T.BusbyBrady Hanson Journal of ASTM InternationalSelected Technical Papers STP1513Effects of Radiation on Nuclear Materialsand the Nuclear Fuel Cycle:24th VolumeJAI Guest Editors:Jeremy T.BusbyBrady D.HansonASTM International100 Barr Harbor DrivePO Box C700West Conshohocken,PA 19428-2959Printed in the U.S.A.ASTM Stock#:STP1513 Library of Congress Cataloging-in-Publication DataISBN:978-0-8031-3425-6ISSN:1050 7515Copyright 2010ASTM INTERNATIONAL,West Conshohocken,PA.All rightsreserved.Thismaterialmaynotbereproducedorcopied,inwholeorinpart,inanyprinted,mechanical,electronic,film,or other distribution and storage media,without thewritten consent of the publisher.Journal of ASTM InternationalJAIScopeThe JAI is a multi-disciplinary forum to serve the international scientific and engineeringcommunity through the timely publication of the results of original research andcritical review articles in the physical and life sciences and engineering technologies.These peer-reviewed papers cover diverse topics relevant to the science and research thatestablish the foundation for standards development withinASTM International.Photocopy RightsAuthorization to photocopy items for internal,personal,or educational classroom use,orthe internal,personal,or educational classroom use of specific clients,is granted byASTM International provided that the appropriate fee is paid toASTM International,100Barr Harbor Drive,P.O.Box C700,West Conshohocken,PA 19428-2959,Tel:610-832-9634;online:http:/www.astm.org/copyright.The Society is not responsible,as a body,for the statements and opinions expressed inthis publication.ASTM International does not endorse any products represented in thispublication.Peer Review PolicyEach paper published in this volume was evaluated by two peer reviewers and at leastoneeditor.Theauthorsaddressedallofthereviewerscommentstothesatisfactionofboththe technical editor(s)and theASTM International Committee on Publications.The quality of the papers in this publication reflects not only the obvious efforts of theauthorsandthetechnicaleditor(s),butalsotheworkofthepeerreviewers.Inkeepingwithlong-standing publication practices,ASTM International maintains the anonymity ofthe peer reviewers.The ASTM International Committee on Publications acknowledgeswith appreciation their dedication and contribution of time and effort on behalf ofASTM International.Citation of PapersWhen citing papers from this publication,the appropriate citation includes the paperauthors,“paper title”,J.ASTM Intl.,volume and number,Paper doi,ASTM International,West Conshohocken,PA,Paper,year listed in the footnote of the paper.A citation isprovided as a footnote on page one of each paper.Printed in Baltimore,MDMay,2010 ForewordTHIS COMPILATION OF THE JOURNAL OF ASTM INTERNATIONAL(JAI),STP1513,on Effects of Radiation on Nuclear Materials and theNuclear Fuel Cycle:24th Volume,contains only the papers published in JAIthat were presented at a symposium in Denver,CO from June 2426,2008 and sponsored by ASTM Committees E10 on Nuclear Technology andits Applications and C26 on the Nuclear Fuel Cycle.The JAI Guest Editors are Jeremy T.Busby,Materials Science andTechnology,Oak Ridge National Laboratory,Oak Ridge,TN,and Brady D.Hanson,Radiochemical Science and Engineering,Pacific NorthwestNational Laboratory,Richland,WA.ContentsOverview.viiInternational Atomic Energy Agency Coordinated Research Projects on StructuralIntegrity of Reactor Pressure VesselsW.L.Server and R.K.Nanstad.1Analysis of the Belgian Surveillance Fracture Toughness Database Using Conventionaland Advanced Master Curve ApproachesE.Lucon,M.Scibetta,and R.Grard.26Final Results from the Crack Initiation and Arrest of Irradiated Steel Materials Projecton Fracture Mechanical Assessments of Pre-Irradiated RPV Steels Used inGerman PWRH.Hein,E.Keim,H.Schnabel,T.Seibert,and A.Gundermann.40Embrittlement Correlation Method for the Japanese Reactor Pressure VesselMaterialsN.Soneda,K.Dohi,A.Nomoto,K.Nishida,and S.Ishino.64Magnox Steel Reactor Pressure Vessel Monitoring SchemesAn OverviewM.R.Wootton,R.Moskovic,C.J.Bolton,and P.E.J.Flewitt.93Investigation of Beltline Welding Seam of the Greifswald WWER-440 Unit 1 ReactorPressure VesselH.W.Viehrig,J.Schuhknecht,U.Rindelhardt,and F.P.Weiss.114Microstructural Characterization of RPV Materials Irradiated to High Fluences at HighFluxN.Soneda,K.Dohi,K.Nishida,A.Nomoto,M.Tomimatsu,and H.Matsuzawa.128Irradiation-Induced Grain-Boundary Solute Segregation and Its Effect on Ductile-to-Brittle Transition Temperature in Reactor Pressure Vessel SteelsY.Nishiyama,M.Yamaguchi,K.Onizawa,A.Iwase,and H.Matsuzawa.152Irradiation-Induced Hardening and Embrittlement of