1、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
2、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 19428-29
3、59Printed 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
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11、ach 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 2
12、426,2008 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,Pacif
13、ic 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 Advanc
14、ed 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 Corr
15、elation 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
16、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
