Skip Nav Destination
100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959 : ASTM International, 1979.
ASTM Selected Technical Papers
Effects of Radiation on Structural Materials
By
JA Sprague,
JA Sprague
editor
1
U.S. Naval Research Laboratory
, Washington, D.C. 20375
; symposium chairman and editor
.
Search for other works by this author on:
David Kramer
David Kramer
editor
2
Atomics International
USA
Search for other works by this author on:
ISBN-10:
0-8031-0327-1
ISBN:
978-0-8031-0327-6
No. of Pages:
694
Publisher:
ASTM International
Publication date:
1979
Description
This volume covers six subject areas: microstructure, fracture of thermal reactor materials, primary damage production and irradiation creep simulation, dosimetry and damage function analysis, mechanical properties and creep.
Sprague, J, & Kramer, D.
Effects of Radiation on Structural Materials. ISBN-10: 0-8031-0327-1
ISBN: 978-0-8031-0327-6
No. of Pages: 694
ISBN (electronic): 978-0-8031-5551-0
Publisher: ASTM International
Published: 1979
Download citation file:
Table of Contents
-
IntroductionByJA SpragueJA Sprague1U.S. Naval Research Laboratory,Washington, D.C. 20375;symposium chairman and editor.Search for other works by this author on:
-
Determination of the Nature of Neutron Irradiation-Induced Dislocation Loops in Magnesium Using Electron Irradiation in the Transmission Electron MicroscopeByA WolfendenA Wolfenden1Guest scientist,Institut für Material- und Festkörperforschung II,Kernforschungszentrum Karlsruhe, 7500 Karlsruhe,. Presently,GermanyWestinghouse Research and Development Center,Pittsburgh, Pa. 15235.Search for other works by this author on:
-
Radiation Effects on Molybdenum Alloys Bombarded by Electrons in a High-Voltage Electron MicroscopeByN Igata,N Igata1Professor, lecturer, and graduate, respectively, Department of Materials Science,University of Tokyo,7-3-1 Hongo, Bunkyo-ku, Tokyo, 113.JapanSearch for other works by this author on:A Kohyama,A Kohyama1Professor, lecturer, and graduate, respectively, Department of Materials Science,University of Tokyo,7-3-1 Hongo, Bunkyo-ku, Tokyo, 113.JapanSearch for other works by this author on:K ItadaniK Itadani1Professor, lecturer, and graduate, respectively, Department of Materials Science,University of Tokyo,7-3-1 Hongo, Bunkyo-ku, Tokyo, 113.JapanSearch for other works by this author on:
-
Microstructural Development During Low-Dose IrradiationByBO Hall,BO Hall1Assistant physicist and metallurgist, respectively, Materials Science Division,Argonne National Laboratory,Argonne, Ill. 60439.Search for other works by this author on:DI PotterDI Potter1Assistant physicist and metallurgist, respectively, Materials Science Division,Argonne National Laboratory,Argonne, Ill. 60439.Search for other works by this author on:
-
Neutron Irradiation-Induced Defect Structures in ZirconiumByA Jostsons,A Jostsons1Leader, Materials Science Section; chief, Materials Division; and experimental officer, respectively,Australian Atomic Energy Commission Research Establishment,Lucas Heights, N.S.W., 2232,.AustraliaSearch for other works by this author on:PM Kelly,PM Kelly1Leader, Materials Science Section; chief, Materials Division; and experimental officer, respectively,Australian Atomic Energy Commission Research Establishment,Lucas Heights, N.S.W., 2232,.AustraliaSearch for other works by this author on:RG Blake,RG Blake1Leader, Materials Science Section; chief, Materials Division; and experimental officer, respectively,Australian Atomic Energy Commission Research Establishment,Lucas Heights, N.S.W., 2232,.AustraliaSearch for other works by this author on:K FarrellK Farrell2Metals and Ceramics Division,Oak Ridge National Laboratory,Oak Ridge, Tenn. 37830.Search for other works by this author on:
-
Irradiation Growth in Zirconium and Its AlloysByDO NorthwoodDO Northwood1Associate professor, Department of Engineering Materials,University of Windsor,Windsor, Ontario,.CanadaN9B3P4Search for other works by this author on:
-
Dependence of Cavity Nucleation Density Upon Gas Implantation Rate and Its Importance in Dual-Beam Irradiation ConditionsByMR Hayns,MR Hayns1Principal scientific officer, senior scientific officer, and senior staff, respectively,UKAEA Harwell,Didcot, Oxon,U.K.Search for other works by this author on:MH Wood,MH Wood1Principal scientific officer, senior scientific officer, and senior staff, respectively,UKAEA Harwell,Didcot, Oxon,U.K.Search for other works by this author on:R BulloughR Bullough1Principal scientific officer, senior scientific officer, and senior staff, respectively,UKAEA Harwell,Didcot, Oxon,U.K.Search for other works by this author on:
-
Response of Inconel 600 to Simulated Fusion Reactor IrradiationByFW WiffenFW Wiffen1Radiation Effects and Microstructural Analysis Group, Metals and Ceramics Division,Oak Ridge National Laboratory,Oak Ridge, Tenn. 37830.Search for other works by this author on:
-
Effects of Neutron Irradiation on the Microstructure of Niobium and Niobium-Base Alloys
-
Effects of Bombarding Ions on the Void Swelling Profile in NickelByJB Whitley,JB Whitley1Nuclear Engineering Department,University of Wisconsin,Madison, Wis. 53706. Dr. Whitley is presently at Sandia Laboratories, Albuquerque, N. Mex.Search for other works by this author on:GL Kulcinski,GL Kulcinski1Nuclear Engineering Department,University of Wisconsin,Madison, Wis. 53706. Dr. Whitley is presently at Sandia Laboratories, Albuquerque, N. Mex.Search for other works by this author on:HV Smith, Jr,HV Smith, Jr1Nuclear Engineering Department,University of Wisconsin,Madison, Wis. 53706. Dr. Whitley is presently at Sandia Laboratories, Albuquerque, N. Mex.Search for other works by this author on:P WilkesP Wilkes1Nuclear Engineering Department,University of Wisconsin,Madison, Wis. 53706. Dr. Whitley is presently at Sandia Laboratories, Albuquerque, N. Mex.Search for other works by this author on:
-
Development of Physically Based Void Swelling Equations for Engineering and Design UseByMR Hayns,MR Hayns1Principal scientific officer and senior staff, respectively, Theoretical Physics Division,A. E. R. E. Harwell,Didcot, Oxon,U. K.Search for other works by this author on:R BulloughR Bullough1Principal scientific officer and senior staff, respectively, Theoretical Physics Division,A. E. R. E. Harwell,Didcot, Oxon,U. K.Search for other works by this author on:
-
A Reassessment of the Role of Stress in Development of Radiation-Induced MicrostructureByFA Garner,FA Garner1Senior scientists,Westinghouse Hanford Company,Richland, Wash. 99352.Search for other works by this author on:WG Wolfer,WG Wolfer2Associate professor,University of Wisconsin,Madison, Wis. 53706.Search for other works by this author on:HR BragerHR Brager1Senior scientists,Westinghouse Hanford Company,Richland, Wash. 99352.Search for other works by this author on:
-
Radiation-Induced Segregation in Nickel-Silicon AlloysByLE Rehn,LE Rehn1Materials Science Division,Argonne National Laboratory,Argonne, Ill. 60439.Search for other works by this author on:PR Okamoto,PR Okamoto1Materials Science Division,Argonne National Laboratory,Argonne, Ill. 60439.Search for other works by this author on:DI Potter,DI Potter1Materials Science Division,Argonne National Laboratory,Argonne, Ill. 60439.Search for other works by this author on:H WiedersichH Wiedersich1Materials Science Division,Argonne National Laboratory,Argonne, Ill. 60439.Search for other works by this author on:
-
An Example of Precipitate Stability in Reactor-Irradiated Nimonic PE16ByDS GellesDS Gelles1Senior scientist,Hanford Engineering Development Laboratory, Westinghouse Hanford Company,Richland, Wash. 99352.Search for other works by this author on:
-
Dependence of Void Formation on Phase Stability in Neutron-Irradiated Type 316 Stainless SteelByHR Brager,HR Brager1Senior scientists,Hanford Engineering Development Laboratory,Richland, Wash. 99352.Search for other works by this author on:FA GarnerFA Garner1Senior scientists,Hanford Engineering Development Laboratory,Richland, Wash. 99352.Search for other works by this author on:
-
Evaluation of Commercial Production A533-B Steel Plates and Weld Deposits with Extra-Low Copper Content for Radiation ResistanceByJR Hawthorne,JR Hawthorne1Research metallurgist, Thermostructural Materials Branch,Naval Research Laboratory,Washington, D.C., 20375.Search for other works by this author on:JJ Koziol,JJ Koziol2Manager,System Materials, andprincipal engineer,Nuclear Power Systems, Combustion Engineering Inc.,Windsor, Conn. 06095.Search for other works by this author on:ST ByrneST Byrne2Manager,System Materials, andprincipal engineer,Nuclear Power Systems, Combustion Engineering Inc.,Windsor, Conn. 06095.Search for other works by this author on:
-
An Empirical Evaluation of the Irradiation Sensitivity of Reactor Pressure Vessel MaterialsByJD Varsik,JD Varsik1Development engineer and principal engineer, respectively,Nuclear Power Systems, C-E Power Systems Division,Combustion Engineering, Inc.,Windsor, Conn. 06095.Search for other works by this author on:ST ByrneST Byrne1Development engineer and principal engineer, respectively,Nuclear Power Systems, C-E Power Systems Division,Combustion Engineering, Inc.,Windsor, Conn. 06095.Search for other works by this author on:
-
Irradiation Behavior of Nickel-Chromium-Molybdenum Type Weld MetalByEN Klausnitzer,EN Klausnitzer1Kraftwerk Union Aktiengesellschaft,Erlangen,.GermanySearch for other works by this author on:A Gerscha,A Gerscha1Kraftwerk Union Aktiengesellschaft,Erlangen,.GermanySearch for other works by this author on:C LeitzC Leitz1Kraftwerk Union Aktiengesellschaft,Erlangen,.GermanySearch for other works by this author on:
-
Exploratory Investigations of Cyclic Irradiation and Annealing Effects on Notch Ductility of A533-B Weld DepositsByJR Hawthorne,JR Hawthorne1Research metallurgist and supervisory mechanical engineers, respectively,Naval Research Laboratory,Washington D.C. 20375.Search for other works by this author on:HE Watson,HE Watson1Research metallurgist and supervisory mechanical engineers, respectively,Naval Research Laboratory,Washington D.C. 20375.Search for other works by this author on:FJ LossFJ Loss1Research metallurgist and supervisory mechanical engineers, respectively,Naval Research Laboratory,Washington D.C. 20375.Search for other works by this author on:
-
Effect and Possibilities of Irradiation Results Error Correction (Demonstrated on the Results of the IAEA Coordinated Program)ByG NagelG Nagel1Gesellschaft für Reaktorsicherheit,Glockengasse 2, 5Cologne 1,.GermanySearch for other works by this author on:
-
Fracture Toughness of Irradiated BerylliumByJM BeestonJM Beeston1Senior scientist,EG&G Idaho, Inc.,Idaho Falls,.IdahoSearch for other works by this author on:
-
Irradiation Creep and Growth in Zirconium During Proton BombardmentByD Faulkner,D Faulkner1Materials Science Branch,Atomic Energy of Canada Limited, Whiteshell Nuclear Research Establishment,Pinawa, Manitoba ROE 1L0,.CanadaSearch for other works by this author on:RJ McElroyRJ McElroy2Atomic Energy Research Establishment,Harwell, Didcot, Oxon OX11 0RA,U.K.Search for other works by this author on:
-
Radiation Damage Effects in 16-MeV Proton and 14-MeV Neutron Irradiated Nickel and NiobiumByRH Jones,RH Jones1Senior research scientist, senior research scientist, and research scientist, respectively,Battelle-Northwest Laboratories,Richland, Wash. 99352.Search for other works by this author on:DL Styris,DL Styris1Senior research scientist, senior research scientist, and research scientist, respectively,Battelle-Northwest Laboratories,Richland, Wash. 99352.Search for other works by this author on:ER BradleyER Bradley1Senior research scientist, senior research scientist, and research scientist, respectively,Battelle-Northwest Laboratories,Richland, Wash. 99352.Search for other works by this author on:
-
Helium Production in Fast Breeder Reactor Out-of-Core Structural ComponentsByRL SimonsRL Simons1Advanced scientist,Hanford Engineering Development Laboratory,Richland, Wash. 99352.Search for other works by this author on:
-
Radiation Damage Function AnalysisByR Gold,R Gold1Fellow scientist, senior scientist, manager, and advanced scientist, respectively,Westing-house Hanford Co., Hanford Engineering Development Laboratory,Richland, Wash. 99352.Search for other works by this author on:EP Lippincott,EP Lippincott1Fellow scientist, senior scientist, manager, and advanced scientist, respectively,Westing-house Hanford Co., Hanford Engineering Development Laboratory,Richland, Wash. 99352.Search for other works by this author on:WN McElroy,WN McElroy1Fellow scientist, senior scientist, manager, and advanced scientist, respectively,Westing-house Hanford Co., Hanford Engineering Development Laboratory,Richland, Wash. 99352.Search for other works by this author on:RL SimonsRL Simons1Fellow scientist, senior scientist, manager, and advanced scientist, respectively,Westing-house Hanford Co., Hanford Engineering Development Laboratory,Richland, Wash. 99352.Search for other works by this author on:
-
Solid-State Track Recorder Materials for Use in Light-Water-Reactor Pressure Vessel Surveillance ExposuresByR Gold,R Gold1Fellow scientist and senior scientist, respectively,Westinghouse Hanford Co., Hanford Engineering Development Laboratory,Richland, Wash. 99352.Search for other works by this author on:JH Roberts,JH Roberts2Consultant; permanent address: Physics Department,Macalester College,St. Paul, Minn. 55105.Search for other works by this author on:FH RuddyFH Ruddy1Fellow scientist and senior scientist, respectively,Westinghouse Hanford Co., Hanford Engineering Development Laboratory,Richland, Wash. 99352.Search for other works by this author on:
-
Microstructure and Tensile Properties of Heavily Irradiated 1100-0 AluminumByK Farrell,K Farrell1Senior research staff,Oak Ridge National Laboratory,Oak Ridge, Tenn. 37830.Search for other works by this author on:AE RichtAE Richt1Senior research staff,Oak Ridge National Laboratory,Oak Ridge, Tenn. 37830.2Union Carbide Corp.,South Charleston, W. Va. 25303.Search for other works by this author on:
-
Tensile Properties of Neutron-Irradiated 6061 Aluminum Alloy in Annealed and Precipitation-Hardened Conditions
-
Tensile Property Correlations for Highly Irradiated 20 Percent Cold-Worked Type 316 Stainless SteelByRL Fish,RL Fish1Senior engineer, advanced engineer, and manager, Mechanical Properties, respectively,Hanford Engineering Development Laboratory, Westinghouse Hanford Company,Richland, Wash. 99352.Search for other works by this author on:NS Cannon,NS Cannon1Senior engineer, advanced engineer, and manager, Mechanical Properties, respectively,Hanford Engineering Development Laboratory, Westinghouse Hanford Company,Richland, Wash. 99352.Search for other works by this author on:GL WireGL Wire1Senior engineer, advanced engineer, and manager, Mechanical Properties, respectively,Hanford Engineering Development Laboratory, Westinghouse Hanford Company,Richland, Wash. 99352.Search for other works by this author on:
-
Low-Cycle Fatigue of Three Irradiated and Unirradiated Vanstar AlloysByGE Korth,GE Korth1Scientists,EG&G Idaho, Inc., Box 1625,Idaho Falls, Idaho 83401.Search for other works by this author on:RE SchmunkRE Schmunk1Scientists,EG&G Idaho, Inc., Box 1625,Idaho Falls, Idaho 83401.Search for other works by this author on:
-
Effects of Neutron Irradiation and Fatigue on Ductility of Stainless Steel DIN 1.4948ByMI de Vries,MI de Vries1Research scientists,Netherlands Energy Research Foundation ECN,Petten (N-H),.The NetherlandsSearch for other works by this author on:B van der Schaaf,B van der Schaaf1Research scientists,Netherlands Energy Research Foundation ECN,Petten (N-H),.The NetherlandsSearch for other works by this author on:HU Staal,HU Staal1Research scientists,Netherlands Energy Research Foundation ECN,Petten (N-H),.The NetherlandsSearch for other works by this author on:LD ElejLD Elej1Research scientists,Netherlands Energy Research Foundation ECN,Petten (N-H),.The NetherlandsSearch for other works by this author on:
-
Estimates of Time-Dependent Fatigue Behavior of Type 316 Stainless Steel Subject to Irradiation Damage in Fast Breeder and Fusion Power Reactor SystemsByCR Brinkman,CR Brinkman1Group leader and research staff members, respectively, Metals and Ceramics Division,Oak Ridge National Laboratory,Oak Ridge, Tenn. 37830.Search for other works by this author on:KC Liu,KC Liu1Group leader and research staff members, respectively, Metals and Ceramics Division,Oak Ridge National Laboratory,Oak Ridge, Tenn. 37830.Search for other works by this author on:ML GrossbeckML Grossbeck1Group leader and research staff members, respectively, Metals and Ceramics Division,Oak Ridge National Laboratory,Oak Ridge, Tenn. 37830.Search for other works by this author on:
-
Fracture Toughness of Irradiated AISI 304 and 316L Stainless SteelsByJ Dufresne,J Dufresne1Senior scientist,Commissariat à l'Energie Atomique, Département de Sûreté Nucléaire,92260 Fontenay-Aux-Roses,.FranceSearch for other works by this author on:B Henry,B Henry2Senior scientist and head, Applied Mechanics Division,Commission of the European Communities, Joint Research Centre, Ispra Establishment,21020 Ispra,.ItalySearch for other works by this author on:H LarssonH Larsson2Senior scientist and head, Applied Mechanics Division,Commission of the European Communities, Joint Research Centre, Ispra Establishment,21020 Ispra,.ItalySearch for other works by this author on:
-
Fracture Toughness of Irradiated Nimonic PE16 at High TemperaturesByRD Nicholson,RD Nicholson1Research officer and section leader, respectively,Central Electricity Generating Board, Berkeley Nuclear Laboratories,Berkeley, Gloucestershire,; R. D. Nicholson is now with theU.K.Central Electricity Generating Board, Marchwood Engineering Laboratories,Southampton,U.K.Search for other works by this author on:RB JonesRB Jones1Research officer and section leader, respectively,Central Electricity Generating Board, Berkeley Nuclear Laboratories,Berkeley, Gloucestershire,; R. D. Nicholson is now with theU.K.Central Electricity Generating Board, Marchwood Engineering Laboratories,Southampton,U.K.Search for other works by this author on:
-
Effects of Irradiation on the Mechanical Properties of Austenitic Stainless Steels Under Dynamic LoadingByC Albertini,C Albertini1Engineers,Commission of the European Communities, Joint Research Centre, ISPRA-Establishment,21020 ISPRA (Varese),.ItalySearch for other works by this author on:A Del Grande,A Del Grande1Engineers,Commission of the European Communities, Joint Research Centre, ISPRA-Establishment,21020 ISPRA (Varese),.ItalySearch for other works by this author on:M MontagnaniM Montagnani1Engineers,Commission of the European Communities, Joint Research Centre, ISPRA-Establishment,21020 ISPRA (Varese),.ItalySearch for other works by this author on:
-
Effects of Irradiation Temperature, Fluence, and Heating Rate on Postirradiation Flow Properties of Cladding Under Simulated Temperature Transient Heating and Deformation ConditionsByNS Cannon,NS Cannon1Advanced engineers,Westinghouse Hanford Company, Hanford Engineering Development Laboratory,Richland, Wash. 99352.Search for other works by this author on:DR DuncanDR Duncan1Advanced engineers,Westinghouse Hanford Company, Hanford Engineering Development Laboratory,Richland, Wash. 99352.Search for other works by this author on:
-
Effects of Irradiation Creep on Ex-Reactor Mechanical PropertiesByDR DuncanDR Duncan1Advanced engineer,Westinghouse Hanford Company, Hanford Engineering Development Laboratory,Richland, Wash. 99352.Search for other works by this author on:
-
Formulation of Constitutive Laws for Deformation During IrradiationByWG WolferWG Wolfer1Associate professor, Department of Nuclear Engineering,University of Wisconsin,Madison, Wis. 53706.Search for other works by this author on:
-
Irradiation Creep in Bending of Cold-Worked AISI 316 Stainless Steel at Low Neutron FluenceByAJ McSherry,AJ McSherry1Senior engineer, Structural Materials,senior engineer, Fuel Pin and Assembly Design,senior engineer, Control Systems Design, andmanager, Structural Materials, respectively,General Electric Co., Advanced Reactor Systems Department,Sunnyvale, Calif.Search for other works by this author on:MR Patel,MR Patel1Senior engineer, Structural Materials,senior engineer, Fuel Pin and Assembly Design,senior engineer, Control Systems Design, andmanager, Structural Materials, respectively,General Electric Co., Advanced Reactor Systems Department,Sunnyvale, Calif.Search for other works by this author on:J Marshall,J Marshall1Senior engineer, Structural Materials,senior engineer, Fuel Pin and Assembly Design,senior engineer, Control Systems Design, andmanager, Structural Materials, respectively,General Electric Co., Advanced Reactor Systems Department,Sunnyvale, Calif.Search for other works by this author on:WK ApplebyWK Appleby1Senior engineer, Structural Materials,senior engineer, Fuel Pin and Assembly Design,senior engineer, Control Systems Design, andmanager, Structural Materials, respectively,General Electric Co., Advanced Reactor Systems Department,Sunnyvale, Calif.Search for other works by this author on:
-
A Comparison of Fuel Pin Deformations with Pressurized Tube Creep TestsByJP Taylor,JP Taylor1Engineer and senior engineers, respectively,Hanford Engineering Development Laboratory,Richland, Washington 99352.Search for other works by this author on:ER Gilbert,ER Gilbert1Engineer and senior engineers, respectively,Hanford Engineering Development Laboratory,Richland, Washington 99352.Search for other works by this author on:AJ LovellAJ Lovell1Engineer and senior engineers, respectively,Hanford Engineering Development Laboratory,Richland, Washington 99352.Search for other works by this author on:
-
Reduction of Irradiation-Induced Creep by Point-Defect Trapping
-
Irradiation Creep Due to Stress-Induced Preferred Absorption of Point Defects in Zirconium Single CrystalsByCH WooCH Woo1Assistant research officer, Materials Science Branch,Whiteshell Nuclear Research Establishment, Atomic Energy of Canada Limited,Pinawa, Manitoba ROE 1LO.CanadaSearch for other works by this author on:
-
In-Reactor Deformation and Fracture of Austenitic Stainless SteelsByEE Bloom,EE Bloom1Metallurgical engineer, Metals and Ceramics Division,Oak Ridge National Laboratory,Oak Ridge, Tenn. 37830.Search for other works by this author on:WG WolferWG Wolfer2Department of Nuclear Engineering,University of Wisconsin,Madison, Wis. 53706.Search for other works by this author on:
Email alerts
Copyright
All rights reserved. This material may not be reproduced or copied, in whole or in part, in any printed, mechanical, electronic, film, or other distribution and storage media, without the written consent of the publisher.
© 1979
ASTM International
