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ASTM Selected Technical Papers
Effects of Radiation on Materials: 12th International Symposium Volume II
By
F. A. Garner,
F. A. Garner
STP Editor
1
Westinghouse Hanford Co.
, Richland, WA 99352,
.US
Search for other works by this author on:
J. S. Perrin
J. S. Perrin
STP Editor
2
Office of Nuclear Waste Isolation
, Columbus, OH 43201,
US
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ISBN:
978-0-8031-0592-8
No. of Pages:
745
Publisher:
ASTM International
Published online:
2018
Published in print:
1985
Garner, FA, & Perrin, JS.
Effects of Radiation on Materials: 12th International Symposium Volume II. ISBN: 978-0-8031-0592-8
No. of Pages: 745
ISBN (electronic): 978-0-8031-7679-9
Publisher: ASTM International
Published: 1985
Download citation file:
Table of Contents
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Fracture Mechanics Methodology for Predicting Critical Flaw Sizes for the First Wall of a Fusion ReactorByWalter G. Reuter,Walter G. Reuter1Principal engineer, senior engineer, and engineering specialist, respectively,EG&G Idaho, Inc.,Idaho Falls, ID 83415USSearch for other works by this author on:Tom E. Rahl,Tom E. Rahl1Principal engineer, senior engineer, and engineering specialist, respectively,EG&G Idaho, Inc.,Idaho Falls, ID 83415USSearch for other works by this author on:Brad J. MerrillBrad J. Merrill1Principal engineer, senior engineer, and engineering specialist, respectively,EG&G Idaho, Inc.,Idaho Falls, ID 83415USSearch for other works by this author on:
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Effects of Irradiation Fluence and Creep on Fracture Toughness of Type 347/348 Stainless SteelByFahmy M. Haggag,Fahmy M. Haggag1Senior engineer, senior engineering specialist, principal engineer, and scientific specialist, respectively,Materials Engineering Branch, Materials Science Division, EG&G Idaho, Inc.,Idaho Falls, ID 83415USSearch for other works by this author on:William L. Server,William L. Server1Senior engineer, senior engineering specialist, principal engineer, and scientific specialist, respectively,Materials Engineering Branch, Materials Science Division, EG&G Idaho, Inc.,Idaho Falls, ID 83415USSearch for other works by this author on:Walter G. Reuter,Walter G. Reuter1Senior engineer, senior engineering specialist, principal engineer, and scientific specialist, respectively,Materials Engineering Branch, Materials Science Division, EG&G Idaho, Inc.,Idaho Falls, ID 83415USSearch for other works by this author on:Joseph M. BeestonJoseph M. Beeston1Senior engineer, senior engineering specialist, principal engineer, and scientific specialist, respectively,Materials Engineering Branch, Materials Science Division, EG&G Idaho, Inc.,Idaho Falls, ID 83415USSearch for other works by this author on:
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Dynamic J-lntegral Toughness and Fractographic Studies of Fast Reactor Irradiated Type 321 Stainless SteelByEdward A. LittleEdward A. Little1Staff scientist,Materials Development Division, AERE Harwell,Oxfordshire, OX11 ORA,GBSearch for other works by this author on:
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Fracture Resistance of Two Ferritic Stainless Steels After Intermediate Temperature IrradiationByJ. Russell Hawthorne,J. Russell Hawthorne1Metallurgist, technician, and metallurgist, respectively,Naval Research Laboratory,Washington, DC 20375USSearch for other works by this author on:James R. Reed,James R. Reed1Metallurgist, technician, and metallurgist, respectively,Naval Research Laboratory,Washington, DC 20375USSearch for other works by this author on:James A. SpragueJames A. Sprague1Metallurgist, technician, and metallurgist, respectively,Naval Research Laboratory,Washington, DC 20375USSearch for other works by this author on:
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Fracture in Helium-Irradiated Type 316 Stainless Steel Microtensile SpecimensByR. David Gerke,R. David Gerke1Graduate student and professor, respectively,Department of Materials Science, University of Virginia,Charlottesville, VA 22901.USSearch for other works by this author on:William A. JesserWilliam A. Jesser1Graduate student and professor, respectively,Department of Materials Science, University of Virginia,Charlottesville, VA 22901.USSearch for other works by this author on:
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Elasto-Plastic Fracture Mechanics Characterization of Type 316H Irradiated Stainless Steel up to 1 dpaByJean Bernard,Jean Bernard1Senior scientist and head, Material Testing Sector, respectively,Commission of the European Communities, Joint Research Centre—Ispra Establishment,21020 Ispra(Va),ITSearch for other works by this author on:Guido VerzelettiGuido Verzeletti1Senior scientist and head, Material Testing Sector, respectively,Commission of the European Communities, Joint Research Centre—Ispra Establishment,21020 Ispra(Va),ITSearch for other works by this author on:
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Fracture Predictions in Zircaloy Fuel CladdingByMansoor A. Khan,Mansoor A. Khan1Graduate research assistant, assistant professor, and alumni associate professor, respectively,Department of Mechanical Engineering, Auburn University,Auburn, AL 36849USSearch for other works by this author on:Nels H. Madsen,Nels H. Madsen1Graduate research assistant, assistant professor, and alumni associate professor, respectively,Department of Mechanical Engineering, Auburn University,Auburn, AL 36849USSearch for other works by this author on:Bryan A. ChinBryan A. Chin1Graduate research assistant, assistant professor, and alumni associate professor, respectively,Department of Mechanical Engineering, Auburn University,Auburn, AL 36849USSearch for other works by this author on:
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Mechanical Burst Properties of Irradiated and Annealed Zircaloy Fuel-Rod CladdingByLarry M. Lowry,Larry M. Lowry1Principal research scientist and research scientist, respectively,Battelle's Columbus Laboratories,Columbus, OH 43201USSearch for other works by this author on:James S. Perrin,James S. Perrin2President,Fracture Control Corporation,Columbus, OH 43229USSearch for other works by this author on:Mark P. LandowMark P. Landow1Principal research scientist and research scientist, respectively,Battelle's Columbus Laboratories,Columbus, OH 43201USSearch for other works by this author on:
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Micro-Macrostructural Mechanical Behavior of Anisotropic Zirconium Alloys Under IrradiationByEduardo J. Savino,Eduardo J. Savino1Head and senior scientists,Radiation Damage Division, Departamento Materiales, Comisión Nacional de Energía Atómica,Buenos Aires,ARSearch for other works by this author on:Santiago HarriagueSantiago Harriague1Head and senior scientists,Radiation Damage Division, Departamento Materiales, Comisión Nacional de Energía Atómica,Buenos Aires,ARSearch for other works by this author on:
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Mechanical Properties of Cold-Worked Type 316 Stainless Steel During Thermal TransientsByRichard Cauvin,Richard Cauvin1Scientists,CEN/SACLAY,Gif-sur-Yvette, Cedex,FRSearch for other works by this author on:Jean-Louis Boutard,Jean-Louis Boutard1Scientists,CEN/SACLAY,Gif-sur-Yvette, Cedex,FRSearch for other works by this author on:Georges AllegraudGeorges Allegraud1Scientists,CEN/SACLAY,Gif-sur-Yvette, Cedex,FRSearch for other works by this author on:
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Low-Dose Irradiation Effects on Creep Properties of Type 304 Stainless Steel Weld Metal, Heat-Affected Zones, and Welded JointsByBob van der SchaafBob van der Schaaf1Research scientist,Netherlands Energy Research Foundation,Petten,NLSearch for other works by this author on:
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Ring Ductility of Irradiated Inconel 706 and Nimonic PE16ByFan-Hsiung Huang,Fan-Hsiung Huang1Senior scientist,Westinghouse Hanford Company,Richland, WA 99352USSearch for other works by this author on:Robert L. FishRobert L. Fish2Staff engineer,Rockwell International,Richland, WA 99352USSearch for other works by this author on:
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Fatigue Behavior at 650°C of 20% Cold-Worked Type 316 Stainless Steel Irradiated at 550°C in the High-Flux Isotope Reactor (HFIR)ByM. L. Grossbeck,M. L. Grossbeck1Research staff members,Metals and Ceramics Division, Oak Ridge National Laboratory,Oak Ridge, TN 37831USSearch for other works by this author on:K. C. LiuK. C. Liu1Research staff members,Metals and Ceramics Division, Oak Ridge National Laboratory,Oak Ridge, TN 37831USSearch for other works by this author on:
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Correlation of Helium Bubble Microstructure to Changes of the Mechanical Properties in Austenitic Stainless SteelsByHerbert Schroeder,Herbert Schroeder1Institut für Festkörperforschung der Kernforschungsanlage Jülich, Postfach 1913,D-5170 Jülich,, Assoziation Euratom-KFADESearch for other works by this author on:Peter BatfalskyPeter Batfalsky1Institut für Festkörperforschung der Kernforschungsanlage Jülich, Postfach 1913,D-5170 Jülich,, Assoziation Euratom-KFADESearch for other works by this author on:
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Neutron Irradiated Mechanical Properties of Some Rapidly Solidified Austenitic Stainless SteelsByOtto K. Harling,Otto K. Harling1Director, research scientist, doctoral candidate, research scientist, and professor, respectively,Nuclear Reactor Laboratory and Department of Materials Science and Engineering, Massachusetts Institute of Technology,Cambridge, MA 02139USSearch for other works by this author on:Marvin Lee,Marvin Lee1Director, research scientist, doctoral candidate, research scientist, and professor, respectively,Nuclear Reactor Laboratory and Department of Materials Science and Engineering, Massachusetts Institute of Technology,Cambridge, MA 02139USSearch for other works by this author on:Dong-Seong Sohn,Dong-Seong Sohn1Director, research scientist, doctoral candidate, research scientist, and professor, respectively,Nuclear Reactor Laboratory and Department of Materials Science and Engineering, Massachusetts Institute of Technology,Cambridge, MA 02139USSearch for other works by this author on:Gordon Kohse,Gordon Kohse1Director, research scientist, doctoral candidate, research scientist, and professor, respectively,Nuclear Reactor Laboratory and Department of Materials Science and Engineering, Massachusetts Institute of Technology,Cambridge, MA 02139USSearch for other works by this author on:Nicholas J. GrantNicholas J. Grant1Director, research scientist, doctoral candidate, research scientist, and professor, respectively,Nuclear Reactor Laboratory and Department of Materials Science and Engineering, Massachusetts Institute of Technology,Cambridge, MA 02139USSearch for other works by this author on:
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Tensile Properties and Swelling of 20% Cold-Worked Type 316 Stainless Steel Irradiated in a High-Flux Isotope Reactor (HFIR)ByR. L. Klueh,R. L. Klueh1Research staff members,Metals and Ceramics Division, Oak Ridge National Laboratory,Oak Ridge, TN 37831USSearch for other works by this author on:M. L. GrossbeckM. L. Grossbeck1Research staff members,Metals and Ceramics Division, Oak Ridge National Laboratory,Oak Ridge, TN 37831USSearch for other works by this author on:
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Mechanical Properties at High Strain Rate of AISI Type 316L Stainless Steel Irradiated to 9.2 dpaByCarlo Albertini,Carlo Albertini1Engineers,Commission of the European Communities, Joint Research Centre, Ispra Establishment,21020 Ispra(Va),ITSearch for other works by this author on:Angelo Del Grande,Angelo Del Grande1Engineers,Commission of the European Communities, Joint Research Centre, Ispra Establishment,21020 Ispra(Va),ITSearch for other works by this author on:Mario MontagnaniMario Montagnani1Engineers,Commission of the European Communities, Joint Research Centre, Ispra Establishment,21020 Ispra(Va),ITSearch for other works by this author on:
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In-Reactor Creep Rupture Experiment in the Materials Open Test Assembly (MOTA)ByRaymond J. Puigh,Raymond J. Puigh1Senior scientist and fellow scientist, respectively,Westinghouse Hanford Company,Richland, WA 99352USSearch for other works by this author on:Robert E. SchenterRobert E. Schenter1Senior scientist and fellow scientist, respectively,Westinghouse Hanford Company,Richland, WA 99352USSearch for other works by this author on:
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Fatigue Crack Growth in Neutron-Irradiated Type 304 and Type 316 Stainless SteelsByMartin I. de Vries,Martin I. de Vries1Research scientist,Netherlands Energy Research Foundation (ECN),Petten,NLSearch for other works by this author on:David J. MichelDavid J. Michel2Supervisory metallurgist,Naval Research Laboratory (NRL),Washington, DC 20375USSearch for other works by this author on:
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Correlation of Yield Strength with Irradiation-Induced Microstructure in AISI Type 316 Stainless SteelByRobert L. Simons,Robert L. Simons1Senior scientist,Hanford Engineering Development Laboratory,Richland, WA 99352USSearch for other works by this author on:Laura A. HulbertLaura A. Hulbert2Graduate student,Department of Applied Mathematics, Cornell University,Ithica, NY 14853USSearch for other works by this author on:
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Relationship Between Irradiation Hardening and Embrittlement of Pressure Vessel SteelsByG. Robert Odette,G. Robert Odette1Professor and post graduate research associate, respectively,Department of Chemical and Nuclear Engineering, University of California,Santa Barbara, CA 93117USSearch for other works by this author on:Peter M. Lombrozo,Peter M. Lombrozo1Professor and post graduate research associate, respectively,Department of Chemical and Nuclear Engineering, University of California,Santa Barbara, CA 93117USSearch for other works by this author on:Richard A. WullaertRichard A. Wullaert2Director,Fracture Control Corporation,Goleta, CA 93117USSearch for other works by this author on:
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Results of the International Atomic Energy Agency (IAEA) Coordinated Research Programs on Irradiation Effects on Advanced Pressure Vessel SteelsByLendell E. Steele,Lendell E. Steele1Head,Thermostructural Materials Branch, Naval Research Laboratory,Washington, DC 20375USSearch for other works by this author on:L. Myrddin Davies,L. Myrddin Davies2Head,Procurement Policy Group, UK Central Electricity Generating Board,London,GBSearch for other works by this author on:Terence Ingham,Terence Ingham3Section leader,Fracture Mechanics-Water Reactors, United Kingdom Atomic Energy Authority, Risley Nuclear Laboratories,Risley,GBSearch for other works by this author on:Milan BrumovskyMilan Brumovsky4Technical consultant,International Atomic Energy Agency,Vienna,ATSearch for other works by this author on:
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Effects of Composition, Microstructure, and Temperature on Irradiation Hardening of Pressure Vessel SteelsByGlenn E. Lucas,Glenn E. Lucas1Associate professor, professor, postgraduate researcher, and senior development engineer, respectively,Department of Chemical and Nuclear Engineering, University of California, Santa Barbara,Santa Barbara, CA 93106USSearch for other works by this author on:G. Robert Odette,G. Robert Odette1Associate professor, professor, postgraduate researcher, and senior development engineer, respectively,Department of Chemical and Nuclear Engineering, University of California, Santa Barbara,Santa Barbara, CA 93106USSearch for other works by this author on:Peter M. Lombrozo,Peter M. Lombrozo1Associate professor, professor, postgraduate researcher, and senior development engineer, respectively,Department of Chemical and Nuclear Engineering, University of California, Santa Barbara,Santa Barbara, CA 93106USSearch for other works by this author on:J. William SheckherdJ. William Sheckherd1Associate professor, professor, postgraduate researcher, and senior development engineer, respectively,Department of Chemical and Nuclear Engineering, University of California, Santa Barbara,Santa Barbara, CA 93106USSearch for other works by this author on:
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Integrated Reactor Vessel Material Surveillance Program for Babcock & Wilcox 177-FA PlantsByArthur L. Lowe, Jr.,Arthur L. Lowe, Jr.1Advisory engineer, principal engineer, and engineer, respectively,Nuclear Power Division, Babcock & Wilcox, a McDermott company,Lynchburg, VA 24505USSearch for other works by this author on:Kenneth E. Moore,Kenneth E. Moore1Advisory engineer, principal engineer, and engineer, respectively,Nuclear Power Division, Babcock & Wilcox, a McDermott company,Lynchburg, VA 24505USSearch for other works by this author on:John D. AadlandJohn D. Aadland1Advisory engineer, principal engineer, and engineer, respectively,Nuclear Power Division, Babcock & Wilcox, a McDermott company,Lynchburg, VA 24505USSearch for other works by this author on:
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Charpy Toughness and Tensile Properties of a Neutron-Irradiated Stainless Steel Submerged-Arc Weld Cladding OverlayByWilliam R. Corwin,William R. Corwin1Metallurgical engineer, metallurgical engineer, and group leader, respectively,Oak Ridge National Laboratory,Oak Ridge, TN 37831USSearch for other works by this author on:Reynold G. Berggren,Reynold G. Berggren1Metallurgical engineer, metallurgical engineer, and group leader, respectively,Oak Ridge National Laboratory,Oak Ridge, TN 37831USSearch for other works by this author on:Randy K. NanstadRandy K. Nanstad1Metallurgical engineer, metallurgical engineer, and group leader, respectively,Oak Ridge National Laboratory,Oak Ridge, TN 37831USSearch for other works by this author on:
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Post-Irradiation Annealing Recovery of Commercial Pressure Vessel SteelsByBruce MacdonaldBruce Macdonald1Senior engineer,Knolls Atomic Power Laboratory, General Electric Company,Schenectady, NY 12301USSearch for other works by this author on:
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Review of In-Service Thermal Annealing of Nuclear Reactor Pressure VesselsByWilliam L. ServerWilliam L. Server1Senior engineering specialist,Idaho National Engineering Laboratory (INEL), EG&G Idaho, Inc.,Idaho Falls, ID 83415USSearch for other works by this author on:
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Strain Aging and Neutron Scattering Studies on Irradiated PWR Pressure Vessel SteelsByEdward A. LittleEdward A. Little1Staff scientist,Materials Development Division, AERE Harwell,Oxfordshire, OX11 ORA,GBSearch for other works by this author on:
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Methods for Extending Life of a Pressurized Water Reactor Vessel After Long-Term Exposure to Fast Neutron RadiationBySamuel P. Grant,Samuel P. Grant1Principal engineer,Carolina Power & Light Company,Raleigh, NC 27602USSearch for other works by this author on:Sam L. EarpSam L. Earp2Consultant in Statistics,Department of Electrical Engineering, Duke University,Durham, NC 27706USSearch for other works by this author on:
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Chemical Composition of Nuclear Reactor Vessel WeldsByKenneth E. Moore,Kenneth E. Moore1Principal engineer, senior principal statistician; and advisory engineer; respectively,Nuclear Power Division, Babcock & Wilcox, a McDermott company,Lynchburg, VA 24505USSearch for other works by this author on:A. S. Heller,A. S. Heller1Principal engineer, senior principal statistician; and advisory engineer; respectively,Nuclear Power Division, Babcock & Wilcox, a McDermott company,Lynchburg, VA 24505USSearch for other works by this author on:Arthur L. Lowe, Jr.Arthur L. Lowe, Jr.1Principal engineer, senior principal statistician; and advisory engineer; respectively,Nuclear Power Division, Babcock & Wilcox, a McDermott company,Lynchburg, VA 24505USSearch for other works by this author on:
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Crack Arrest Behavior of Pressure Vessel Plates and Weldments as Influenced by Radiation and Copper ContentByCharles W. Marschall,Charles W. Marschall1Principal research scientist, research leader, and research scientist, respectively,Battelle Columbus Laboratories,Columbus, OH 43201USSearch for other works by this author on:Alan R. Rosenfield,Alan R. Rosenfield1Principal research scientist, research leader, and research scientist, respectively,Battelle Columbus Laboratories,Columbus, OH 43201USSearch for other works by this author on:Mark P. Landow,Mark P. Landow1Principal research scientist, research leader, and research scientist, respectively,Battelle Columbus Laboratories,Columbus, OH 43201USSearch for other works by this author on:Thomas R. Mager,Thomas R. Mager2Consulting engineer and senior engineer, respectively,Westinghouse Electric Corporation,Pittsburgh, PA 15230USSearch for other works by this author on:Randy G. Lott,Randy G. Lott2Consulting engineer and senior engineer, respectively,Westinghouse Electric Corporation,Pittsburgh, PA 15230USSearch for other works by this author on:Samuel W. Tagart, Jr.Samuel W. Tagart, Jr.3Technical specialist,Electric Power Research Institute,Palo Alto, CA 94303USSearch for other works by this author on:
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Relationship of Yield Strength and Upper-Shelf Impact Energy Changes for Irradiated Reactor Vessel SteelByStephen T. Byrne,Stephen T. Byrne1Supervisor and senior development engineer, respectively,Nuclear Power Systems Division, Combustion Engineering, Inc.,Windsor, CT 06095USSearch for other works by this author on:Ronald C. PirekRonald C. Pirek1Supervisor and senior development engineer, respectively,Nuclear Power Systems Division, Combustion Engineering, Inc.,Windsor, CT 06095USSearch for other works by this author on:
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Analysis of Charpy V-Notch Impact Toughness of Irradiated A533-B Class 1 Plate and Four Submerged-Arc WeldsByReynold G. Berggren,Reynold G. Berggren1Metallurgical engineers,Metals and Ceramics Division, Oak Ridge National Laboratory,Oak Ridge, TN 37831USSearch for other works by this author on:J. Russell Hawthorne,J. Russell Hawthorne2Senior scientist,Materials Engineering Associates,Lanham, MD 20706USSearch for other works by this author on:Randy K. NanstadRandy K. Nanstad1Metallurgical engineers,Metals and Ceramics Division, Oak Ridge National Laboratory,Oak Ridge, TN 37831USSearch for other works by this author on:
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Effects of Neutron Irradiation on Fracture Toughness of A533-B Class 1 Plate and Four Submerged-Arc WeldsByBlaine H. Menke,Blaine H. Menke1Senior engineer and laboratory manager, respectively,Materials Engineering Associates, Inc.,Lanham, MD 20706USSearch for other works by this author on:John J. McGowan,John J. McGowan2Mechanical engineer; metallurgical engineer; andleader,Pressure Vessel Technology Group, respectively,Oak Ridge National Laboratory,Oak Ridge, TN 37830USSearch for other works by this author on:Reynold G. Berggren,Reynold G. Berggren2Mechanical engineer; metallurgical engineer; andleader,Pressure Vessel Technology Group, respectively,Oak Ridge National Laboratory,Oak Ridge, TN 37830USSearch for other works by this author on:Randy K. Nanstad,Randy K. Nanstad2Mechanical engineer; metallurgical engineer; andleader,Pressure Vessel Technology Group, respectively,Oak Ridge National Laboratory,Oak Ridge, TN 37830USSearch for other works by this author on:Kevin C. MillerKevin C. Miller1Senior engineer and laboratory manager, respectively,Materials Engineering Associates, Inc.,Lanham, MD 20706USSearch for other works by this author on:
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Fracture Toughness Characterization of Irradiated Low Upper-Shelf WeldsByAllen L. Hiser,Allen L. Hiser1Mechanical engineer, technical director, and senior engineer, respectively,Materials Engineering Associates, Inc.,Lanham, MD 20706USSearch for other works by this author on:Frank J. Loss,Frank J. Loss1Mechanical engineer, technical director, and senior engineer, respectively,Materials Engineering Associates, Inc.,Lanham, MD 20706USSearch for other works by this author on:Blaine H. MenkeBlaine H. Menke1Mechanical engineer, technical director, and senior engineer, respectively,Materials Engineering Associates, Inc.,Lanham, MD 20706USSearch for other works by this author on:
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Fracture Toughness of Accelerated Irradiated Submerged-Arc Weld MetalByRobert H. Priest,Robert H. Priest1Research officers,Central Electricity Generating Board, Berkeley Nuclear Laboratories,Berkeley, Gloucestershire,GBSearch for other works by this author on:William Charnock,William Charnock2Research officer,Central Electricity Generating Board, North Western Region Scientific Services Department,Manchester,GBSearch for other works by this author on:Brian K. NealeBrian K. Neale1Research officers,Central Electricity Generating Board, Berkeley Nuclear Laboratories,Berkeley, Gloucestershire,GBSearch for other works by this author on:
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Notch Ductility and Fracture Toughness Degradation of Pressure Vessel Steel Reference Plates from Pool Side Facility (PSF) Irradiation CapsulesByJ. Russell Hawthorne,J. Russell Hawthorne1Senior metallurgist, mechanical engineer, and mechanical engineer, respectively,Materials Engineering Associates, Inc.,Lanham, MD 20706USSearch for other works by this author on:Blaine H. Menke,Blaine H. Menke1Senior metallurgist, mechanical engineer, and mechanical engineer, respectively,Materials Engineering Associates, Inc.,Lanham, MD 20706USSearch for other works by this author on:Allen L. HiserAllen L. Hiser1Senior metallurgist, mechanical engineer, and mechanical engineer, respectively,Materials Engineering Associates, Inc.,Lanham, MD 20706USSearch for other works by this author on:
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Calculation of Displacement and Helium Production at the Clinton P. Anderson Los Alamos Meson Physics Facility (LAMPF) Irradiation FacilityByMonroe S. Wechsler,Monroe S. Wechsler1Professor, Material Science and Engineering and Nuclear Engineering; nuclear engineer; and associate group leader; respectively,Los Alamos National Laboratory,Los Alamos, NM 87545USSearch for other works by this author on:Dorothy R. Davidson,Dorothy R. Davidson1Professor, Material Science and Engineering and Nuclear Engineering; nuclear engineer; and associate group leader; respectively,Los Alamos National Laboratory,Los Alamos, NM 87545USSearch for other works by this author on:Lawrence R. Greenwood,Lawrence R. Greenwood2Physicist,Argonne National Laboratory,Argonne, IL 60439USSearch for other works by this author on:Walter F. SommerWalter F. Sommer1Professor, Material Science and Engineering and Nuclear Engineering; nuclear engineer; and associate group leader; respectively,Los Alamos National Laboratory,Los Alamos, NM 87545USSearch for other works by this author on:
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Measured Radiation Environment at the Clinton P. Anderson Los Alamos Meson Physics Facility (LAMPF) Irradiation FacilityByDorothy R. Davidson,Dorothy R. Davidson1Nuclear engineer, nuclear chemist, and associate group leader, respectively,Los Alamos National Laboratory,Los Alamos, NM 87545.USSearch for other works by this author on:Lawrence R. Greenwood,Lawrence R. Greenwood2Physicist,Argonne National Laboratory,Argonne, IL 60439.USSearch for other works by this author on:Robert C. Reedy,Robert C. Reedy1Nuclear engineer, nuclear chemist, and associate group leader, respectively,Los Alamos National Laboratory,Los Alamos, NM 87545.USSearch for other works by this author on:Walter F. SommerWalter F. Sommer1Nuclear engineer, nuclear chemist, and associate group leader, respectively,Los Alamos National Laboratory,Los Alamos, NM 87545.USSearch for other works by this author on:
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A Modified Tritium Trick Technique for Doping Vanadium Alloys with HeliumByDavid N. Braski,David N. Braski1Research scientist,Metals and Ceramics Division, Oak Ridge National Laboratory,Oak Ridge, TN 37831USSearch for other works by this author on:Dan W. RameyDan W. Ramey2Research development specialist,Operations Division, Oak Ridge National Laboratory,Oak Ridge, TN 37831USSearch for other works by this author on:
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A Transmission Electron Microscopy Study of the Structure and Annealing Behavior of Copper-Krypton DepositsByJohn H. Evans,John H. Evans1Principal scientific officer, scientific officer, and principal scientific officer, respectively,Materials Development Division, AERE Harwell,Oxon, 0X11 ORA,GBSearch for other works by this author on:Robert Williamson,Robert Williamson1Principal scientific officer, scientific officer, and principal scientific officer, respectively,Materials Development Division, AERE Harwell,Oxon, 0X11 ORA,GBSearch for other works by this author on:Derek S. WhitmellDerek S. Whitmell1Principal scientific officer, scientific officer, and principal scientific officer, respectively,Materials Development Division, AERE Harwell,Oxon, 0X11 ORA,GBSearch for other works by this author on:
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Radiation Effects on Resins and Zeolites at Three Mile Island Unit IIByJames K. Reilly,James K. Reilly1Nuclear engineer,U. S. Department of Energy,Middletown, PA 17057USSearch for other works by this author on:Philip J. Grant,Philip J. Grant2Chief,Technical Support Section, TMI Program Office, U. S. Nuclear Regulatory Commission,Middletown, PA 17057USSearch for other works by this author on:Geoffrey J. Quinn,Geoffrey J. Quinn3Program manager,EG&G Idaho Inc.,Idaho Falls, ID 83415USSearch for other works by this author on:Thomas C. Runion,Thomas C. Runion4Consultant, Middletown, PA 17057USSearch for other works by this author on:Kenneth J. HofstetterKenneth J. Hofstetter5Radio-Chemical Engineering Supervisor,General Public Utilities Nuclear Corporation,Middletown, PA 17057USSearch for other works by this author on:
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© 1985
ASTM International
