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ASTM Selected Technical Papers
Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels: An International Study
By
LE Steele
LE Steele
1
Head
, Thermostructural Materials Branch, Material Science & Technology Division, Naval Research Laboratory
, Washington, D.C.
; Specialist Meeting Chairman and editor
.
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ISBN-10:
0-8031-0263-1
ISBN:
978-0-8031-0263-7
No. of Pages:
228
Publisher:
ASTM International
Publication date:
1983
Description
STP 819 presents an international view on this subject drawing particularly on experience in laboratory studies and operating nuclear power plants in the USA and Europe. Of particular interest to the reader is the information imparted on reactor vessel embrittlement determination through periodic surveillance of specimens exposed in operating nuclear plants.
Steele, L.
Radiation Embrittlement and Surveillance of Nuclear Reactor Pressure Vessels: An International Study. ISBN-10: 0-8031-0263-1
ISBN: 978-0-8031-0263-7
No. of Pages: 228
ISBN (electronic): 978-0-8031-4885-7
Publisher: ASTM International
Published: 1983
Download citation file:
Table of Contents
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IntroductionByLE SteeleLE Steele1Head,Thermostructural Materials Branch, Material Science & Technology Division, Naval Research Laboratory,Washington, D.C.;Specialist Meeting Chairman and editor.Search for other works by this author on:
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NRC Safety Research Priorities for Reactor Vessel Embrittlement, Annealing, and Surveillance DosimetryByCZ Serpan, JrCZ Serpan, Jr1Chief,Materials Engineering Branch, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission,Washington, DC, 20555.Search for other works by this author on:
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West German Research Programs on Irradiation Effects on Reactor Pressure VesselsByK KussmaulK Kussmaul1Professor and Director,Staatliche Materialprüfungsanstalt, University of Stuttgart,Stuttgart,.West GermanySearch for other works by this author on:
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Irradiation Embrittlement of Pressure Vessel Steels: A Review of Activities in FranceByP PetrequinP Petrequin1Saclay Nuclear Research Center, Atomic Energy Commission,Gif-sur-Yvette,.FranceSearch for other works by this author on:
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Determination of Neutron Damage Parameters for Irradiation EmbrittlementByEP Lippincott,EP Lippincott1Senior Scientist and Manager of Irradiation Environment, respectively,Westinghouse Hanford Company, Hanford Engineering Development Laboratory,Richland, WA 99352.Search for other works by this author on:WN McElroyWN McElroy1Senior Scientist and Manager of Irradiation Environment, respectively,Westinghouse Hanford Company, Hanford Engineering Development Laboratory,Richland, WA 99352.Search for other works by this author on:
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Effect of Irradiation on Elastic-Plastic Toughness of Pressure Vessel SteelsByP Soulat,P Soulat1Saclay Nuclear Research Center, Atomic Energy Commission,Gif-sur-Yvette,.FranceSearch for other works by this author on:P Petrequin,P Petrequin1Saclay Nuclear Research Center, Atomic Energy Commission,Gif-sur-Yvette,.FranceSearch for other works by this author on:B HoussinB Houssin2Framatome, Paris la Defense,.FranceSearch for other works by this author on:
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Specific Problems of Reactor Pressure Vessels Related to Irradiation EffectsByK KussmaulK Kussmaul1Professor and Director,Staatliche Materialprüfungsanstalt, University of Stuttgart,Stuttgart,.West GermanySearch for other works by this author on:
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Status of Knowledge of Radiation Embrittlement in U.S. Reactor Pressure Vessel SteelsByJR HawthorneJR Hawthorne1Research Metallurgist,Naval Research Laboratory,Washington, D.C. 20375.Search for other works by this author on:
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Irradiation Experiments in the Testing Nuclear Power Plant VAKByJ Föhl,J Föhl1Staatliche Materialprüfungsanstalt (MPA), University of Stuttgart,.West GermanySearch for other works by this author on:CH Leitz,CH Leitz2Kraftwerkunion AG (KWU),Erlangen,.West GermanySearch for other works by this author on:D AndersD Anders3Forschungszentrum Geesthacht (GKSS),.West GermanySearch for other works by this author on:
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Role of the Active Defect Complex in the Neutron Embrittlement and Thermal Recovery of High-Copper Reactor Pressure Vessel SteelsByJP HightonJP Highton1Senior Lecturer,Royal Naval College,Greenwich,.EnglandSearch for other works by this author on:
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Survey of Utility Experience with Reactor Vessel SurveillanceByS RothsteinS Rothstein1Chemical and Metallurgical Engineer,Consolidated Edison Co.,New York, N. Y. 10003.Search for other works by this author on:
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Thermal Aging Capsule Results from Oconee Nuclear Station—Unit 1ByAL Lowe, JrAL Lowe, Jr1Advisory Engineer,The Babcock & Wilcox Company,Lynchburg, Va. 24505.Search for other works by this author on:
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Assessing Steady-State Neutron Exposure Effects Through Analyses of Reactor Vessel Surveillance DataByTR Mager,TR Mager1Manager,Metallurgical and Nondestructive Analysis, Nuclear Technology Division, Westinghouse Electric Corporation,Pittsburgh, Pa. 15230.Search for other works by this author on:TU Martson,TU Martson2Project Manager,Electric Power Research Institute,Palo Alto, Calif. 94303.Search for other works by this author on:SE YanichkoSE Yanichko3Senior Engineer,Nuclear Technology Division, Westinghouse Electric Corporation,Pittsburgh, Pa. 15230.Search for other works by this author on:
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Selection of Specimen Types for Irradiation Surveillance ProgramsByT Varga,T Varga1Professor and Head,Institute for Testing and Research in Materials Technology, Technical University of Vienna,; alsoAustriaSwiss Nuclear Safety Department,Würenlingen,.SwitzerlandSearch for other works by this author on:D-H NjoD-H Njo2Scientific Adjunct,Swiss Nuclear Safety Department,Würenlingen,.SwitzerlandSearch for other works by this author on:
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A Fracture Energy Criterion for Irradiation Research and SurveillanceByF Gillemot,F Gillemot1Scientific Assistants,Central Research Institute for Physics,Budapest,.HungarySearch for other works by this author on:A KapitányA Kapitány1Scientific Assistants,Central Research Institute for Physics,Budapest,.HungarySearch for other works by this author on:
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Problems in the Evaluation of Reactor Vessel Surveillance CapsulesByJS PerrinJS Perrin1President,Fracture Control Corporation,Goleta, Calif. 93117.Search for other works by this author on:
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A Service Laboratory's View of the Status and Direction of Reactor Vessel SurveillanceByEB NorrisEB Norris1Southwest Research Institute,San Antonio, Tex. 78284.Search for other works by this author on:
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© 1983
ASTM International
