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ASTM Selected Technical Papers
Zirconium in the Nuclear Industry: Eighth International Symposium
By
CM Eucken,
CM Eucken
1
Teledyne Wah Chang Albany
, Albany, OR 97321-036
; symposium chairman and editor
.
Search for other works by this author on:
LFP Van Swam
LFP Van Swam
2
Advanced Nuclear Fuels Corp.
?Richland, WA 99352-0130
; symposium chairman and editor
.
Search for other works by this author on:
ISBN-10:
0-8031-1199-1
ISBN:
978-0-8031-1199-8
No. of Pages:
791
Publisher:
ASTM International
Publication date:
1989
Description
Topics include:
• Behavior of Pressure Tubes
• Corrosion
• Nodular Corrosion
• Basic Metallurgy
• Mechanical Behavior, Stress Corrosion, and Fatigue
• Creep and Growth
Corrosion behavior is given special emphasis.
Eucken, C, & Van Swam, L.
Zirconium in the Nuclear Industry: Eighth International Symposium. ISBN-10: 0-8031-1199-1
ISBN: 978-0-8031-1199-8
No. of Pages: 791
ISBN (electronic): 978-0-8031-5084-3
Publisher: ASTM International
Published: 1989
Download citation file:
Table of Contents
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Corrosion and Hydriding of N Reactor Pressure TubesByDD Lanning,DD Lanning1Principal engineer and senior staff scientist, respectively,Battelle—Pacific Northwest Laboratory, P.O. Box 1970,Richland, WA 99352.Search for other works by this author on:AB Johnson, Jr,AB Johnson, Jr1Principal engineer and senior staff scientist, respectively,Battelle—Pacific Northwest Laboratory, P.O. Box 1970,Richland, WA 99352.Search for other works by this author on:DJ Trimble,DJ Trimble2Westinghouse Hanford Company, P.O. Box 1970,Richland, WA 99352.Search for other works by this author on:SM BoydSM Boyd2Westinghouse Hanford Company, P.O. Box 1970,Richland, WA 99352.Search for other works by this author on:
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Oxidation and Deuterium Uptake of Zr-2.5Nb Pressure Tubes in CANDU-PHW ReactorsByVF Urbanic,VF Urbanic1Research scientist,Atomic Energy of Canada Ltd., Chalk River Nuclear Laboratories,Chalk River Ontario K0J IJ0,.CanadaSearch for other works by this author on:BD Warr,BD Warr2Research scientists,Ontario Hydro Research,Toronto, Ontario,.CanadaSearch for other works by this author on:A Manolescu,A Manolescu2Research scientists,Ontario Hydro Research,Toronto, Ontario,.CanadaSearch for other works by this author on:CK Chow,CK Chow3Research scientist,Atomic Energy of Canada Ltd., Whiteshell Nuclear Research Establishment,Pinawa, Manitoba,.CanadaSearch for other works by this author on:MW ShanahanMW Shanahan4Technical superintendent,Ontario Hydro, Central Nuclear Services,Toronto, Ontario,.CanadaSearch for other works by this author on:
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Evaluation of Zircaloy-2 Pressure Tubes from NPDByCE Coleman,CE Coleman1Atomic Energy of Canada Limited Research Company, Chalk River Nuclear Laboratories,Chalk River, Ontario KOJ 1J0,.CanadaSearch for other works by this author on:BA Cheadle,BA Cheadle1Atomic Energy of Canada Limited Research Company, Chalk River Nuclear Laboratories,Chalk River, Ontario KOJ 1J0,.CanadaSearch for other works by this author on:AR Causey,AR Causey1Atomic Energy of Canada Limited Research Company, Chalk River Nuclear Laboratories,Chalk River, Ontario KOJ 1J0,.CanadaSearch for other works by this author on:PCK Chow,PCK Chow2Atomic Energy of Canada Limited, Research Company, Whiteshell Nuclear Research Establish-ment,Pinawa, Manitoba ROE 1L0,.CanadaSearch for other works by this author on:PH Davies,PH Davies1Atomic Energy of Canada Limited Research Company, Chalk River Nuclear Laboratories,Chalk River, Ontario KOJ 1J0,.CanadaSearch for other works by this author on:MD McManus,MD McManus1Atomic Energy of Canada Limited Research Company, Chalk River Nuclear Laboratories,Chalk River, Ontario KOJ 1J0,.CanadaSearch for other works by this author on:DK Rodgers,DK Rodgers1Atomic Energy of Canada Limited Research Company, Chalk River Nuclear Laboratories,Chalk River, Ontario KOJ 1J0,.CanadaSearch for other works by this author on:S Sagat,S Sagat1Atomic Energy of Canada Limited Research Company, Chalk River Nuclear Laboratories,Chalk River, Ontario KOJ 1J0,.CanadaSearch for other works by this author on:G van DrunenG van Drunen1Atomic Energy of Canada Limited Research Company, Chalk River Nuclear Laboratories,Chalk River, Ontario KOJ 1J0,.CanadaSearch for other works by this author on:
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Growth, Fracture, and Nondestructive Evaluation of Hydride Blisters in Zr-2.5 Nb Pressure TubesByM Leger,M Leger1Head, Fracture Mechanisms Unit, Materials Integrity Section, andengineerNondestructive and Fracture Evaluation Section, respectively,Ontario Hydro Research Division,800 Kipling Ave., Toronto, Ontario M8Z 5S4,.CanadaSearch for other works by this author on:GD Moan,GD Moan2Metallurgist, Materials Engineering Department,Atomic Energy of Canada, CANDU Operations,Toronto, Ontario,.CanadaSearch for other works by this author on:AC Wallace,AC Wallace1Head, Fracture Mechanisms Unit, Materials Integrity Section, andengineerNondestructive and Fracture Evaluation Section, respectively,Ontario Hydro Research Division,800 Kipling Ave., Toronto, Ontario M8Z 5S4,.CanadaSearch for other works by this author on:NJ WatsonNJ Watson3Engineer, Inspection and Maintenance,Ontario Hydro, Technical and Training Services Division,Toronto, Ontario,.CanadaSearch for other works by this author on:
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Effects of Hydride Morphology on Zr-2.5Nb Fracture ToughnessByAC Wallace,AC Wallace1Engineers,Ontario Hydro Research Division,800 Kipling Ave., Toronto,.CanadaSearch for other works by this author on:GK Shek,GK Shek1Engineers,Ontario Hydro Research Division,800 Kipling Ave., Toronto,.CanadaSearch for other works by this author on:OE LepikOE Lepik1Engineers,Ontario Hydro Research Division,800 Kipling Ave., Toronto,.CanadaSearch for other works by this author on:
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Effects of Loading and Thermal Maneuvers on Delayed Hydride Cracking in Zr-2.5 Nb AlloysByGK Shek,GK Shek1Metallurgical engineer and technical supervisor, respectively,Ontario Hydro,700 University Ave., Toronto, Ontario MG5 1X6,.CanadaSearch for other works by this author on:DB GrahamDB Graham1Metallurgical engineer and technical supervisor, respectively,Ontario Hydro,700 University Ave., Toronto, Ontario MG5 1X6,.CanadaSearch for other works by this author on:
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Influence of Chemical Composition on Uniform Corrosion of Zirconium-Base Alloys in Autoclave TestsByCM Eucken,CM Eucken1Manager, Process Development, and Senior Metallurgist, respectively,Teledyne Wah Chang Albany, P.O. Box 460,Albany, OR 97321.Search for other works by this author on:PT Finden,PT Finden1Manager, Process Development, and Senior Metallurgist, respectively,Teledyne Wah Chang Albany, P.O. Box 460,Albany, OR 97321.Search for other works by this author on:S Trapp-Pritsching,S Trapp-Pritsching2Senior Engineer and Senior Director, respectively,Kraftwerk Union AG-B-22,Hammerbacherstrasse 12+14, P.O. Box 3220,Erlangen, D-8520,.Federal Republic of GermanySearch for other works by this author on:HG WeidingerHG Weidinger2Senior Engineer and Senior Director, respectively,Kraftwerk Union AG-B-22,Hammerbacherstrasse 12+14, P.O. Box 3220,Erlangen, D-8520,.Federal Republic of GermanySearch for other works by this author on:
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Correlation Between 400°C Steam Corrosion Behavior, Heat Treatment, and Microstructure of Zircaloy-4 TubingByT Thorvaldsson,T Thorvaldsson1Manager of physical metallurgy, manager product development special metals, and physical metallurgist, respectively,AB Sandvik Steel, R&D Centre,S-811 81,.SwedenSearch for other works by this author on:T Andersson,T Andersson1Manager of physical metallurgy, manager product development special metals, and physical metallurgist, respectively,AB Sandvik Steel, R&D Centre,S-811 81,.SwedenSearch for other works by this author on:A Wilson,A Wilson1Manager of physical metallurgy, manager product development special metals, and physical metallurgist, respectively,AB Sandvik Steel, R&D Centre,S-811 81,.SwedenSearch for other works by this author on:A WardleA Wardle2Research scientist,University of Birmingham,Birmingham,.EnglandSearch for other works by this author on:
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Influence of the Manufacturing Process on the Corrosion Resistance of Zircaloy-4 CladdingByJJ Schemel,JJ Schemel1Vice-president,Research and Engineering, Sandvik Special Metals Corp., P.O. Box 6027,Kennewick, WA 99336.Search for other works by this author on:D Charquet,D Charquet2Assistant vice-president and research engineer, respectively,CEZUS Research,Ugine,.FranceSearch for other works by this author on:J-F WadierJ-F Wadier2Assistant vice-president and research engineer, respectively,CEZUS Research,Ugine,.FranceSearch for other works by this author on:
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A Laboratory Method to Predict Hydriding Properties of Zirconium Alloys Under IrradiationByAB Johnson, Jr,AB Johnson, Jr1Battelle-Pacific Northwest Laboratory, P.O. Box 999,Richland, WA 99352.Search for other works by this author on:IS Levy,IS Levy1Battelle-Pacific Northwest Laboratory, P.O. Box 999,Richland, WA 99352.Search for other works by this author on:DD Lanning,DD Lanning1Battelle-Pacific Northwest Laboratory, P.O. Box 999,Richland, WA 99352.Search for other works by this author on:FS Gerber,FS Gerber1Battelle-Pacific Northwest Laboratory, P.O. Box 999,Richland, WA 99352.Search for other works by this author on:DJ TrimbleDJ Trimble2Westinghouse Hanford Company, P.O. Box 1970,Richland, WA 99352.Search for other works by this author on:
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Development of a Mechanistic Model to Assess the External Corrosion of the Zircaloy Claddings in PWRsByP Billot,P Billot1Fellow Engineer, head of Atomic Energy Commission, and fellow engineer, respectively,Commissariat A L'Energie Atomique, CEN Cardarache,13108 St. Paul-Lez-Durance, Cedex,.FranceSearch for other works by this author on:P Beslu,P Beslu1Fellow Engineer, head of Atomic Energy Commission, and fellow engineer, respectively,Commissariat A L'Energie Atomique, CEN Cardarache,13108 St. Paul-Lez-Durance, Cedex,.FranceSearch for other works by this author on:A Giordano,A Giordano1Fellow Engineer, head of Atomic Energy Commission, and fellow engineer, respectively,Commissariat A L'Energie Atomique, CEN Cardarache,13108 St. Paul-Lez-Durance, Cedex,.FranceSearch for other works by this author on:J ThomazetJ Thomazet2Engineering specialist,Fragema, Framatome, Division Combustible, B.P. 3083-69398,LyonCedex 3,.FranceSearch for other works by this author on:
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Lithium Uptake and the Accelerated Corrosion of Zirconium AlloysByN Ramasubramanian,N Ramasubramanian1Research officer and technical assistants, respectively,Atomic Energy of Canada Ltd., Chalk River Nuclear Laboratories,Chalk River, Ontario K0J 1J0,.CanadaSearch for other works by this author on:N Precoanin,N Precoanin1Research officer and technical assistants, respectively,Atomic Energy of Canada Ltd., Chalk River Nuclear Laboratories,Chalk River, Ontario K0J 1J0,.CanadaSearch for other works by this author on:VC LingVC Ling1Research officer and technical assistants, respectively,Atomic Energy of Canada Ltd., Chalk River Nuclear Laboratories,Chalk River, Ontario K0J 1J0,.CanadaSearch for other works by this author on:
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Microstructure and Corrosion Studies for Optimized PWR and BWR Zircaloy CladdingByF Garzarolli,F Garzarolli1Deputy director, manager, and senior director, respectively,Siemens AG, KWU-Group,D-8520 Erlangen,.West GermanySearch for other works by this author on:E Steinberg,E Steinberg1Deputy director, manager, and senior director, respectively,Siemens AG, KWU-Group,D-8520 Erlangen,.West GermanySearch for other works by this author on:HG WeidingerHG Weidinger1Deputy director, manager, and senior director, respectively,Siemens AG, KWU-Group,D-8520 Erlangen,.West GermanySearch for other works by this author on:
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Corrosion Performance of Zircaloy-2 and Zircaloy-4 PWR Fuel CladdingByP Rudling,P Rudling1Staff engineer,ABB ATOM, Fuel Division,S-72163 Vaskerån,.SwedenSearch for other works by this author on:H Pettersson,H Pettersson2Swedish State Power Board, Nuclear Fuel Technology,S16287 Vallingby,.SwedenSearch for other works by this author on:T Andersson,T Andersson3Research and Development Center, AB Sandvik Steel,5-811 81 Sandviken,.SwedenSearch for other works by this author on:T ThorvaldssonT Thorvaldsson3Research and Development Center, AB Sandvik Steel,5-811 81 Sandviken,.SwedenSearch for other works by this author on:
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Development of a Cladding Alloy for High BurnupByGP Sabol,GP Sabol1Managerof Materials Applications Department,Westinghouse Electric Corporation, Research and Development Center,Pittsburgh, PA 15235.Search for other works by this author on:GR Kilp,GR Kilp2Advisory engineer,Westinghouse Electric Corporation, CNFD,Monroeville, PA 15146.Search for other works by this author on:MG Balfour,MG Balfour3Senior engineer,Westinghouse Electric Corporation, CNFD,Monroeville, PA 15146.Search for other works by this author on:E RobertsE Roberts4Manager,Materials and Mechanical Process Development, Westinghouse Electric Corporation, CNFD,Columbia, SC 29250.Search for other works by this author on:
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Enhanced Low-Temperature Oxidation of Zirconium Alloys Under IrradiationByB Cox,B Cox1Program consultant and metallurgical engineer, respectively, Reactor Materials Division,Chalk River Nuclear Laboratories,Chalk River, Ontario KOJ 1J0,.Canada2Present title and addressprofessor of nuclear engineering,University of Toronto, Centre for Nuclear Engineering,184 College St., Toronto, Ontario, M5S 1A4.Search for other works by this author on:V FidlerisV Fidleris1Program consultant and metallurgical engineer, respectively, Reactor Materials Division,Chalk River Nuclear Laboratories,Chalk River, Ontario KOJ 1J0,.CanadaSearch for other works by this author on:
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Internal Hydriding in Irradiated Defected Zircaloy Fuel RodsByJC ClaytonJC Clayton1Fellow scientist,Westinghouse Electric Corporation, Bettis Atomic Power Laboratory,West Mifflin, PA 15122.Search for other works by this author on:
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A Systematic Survey of the Factors Affecting Zircaloy Nodular CorrosionByK Ogata,K Ogata1Research Department,Nippon Nuclear Fuel Development Co., Ltd.,Ibaraki,.JapanSearch for other works by this author on:M Yoshitsugu,M Yoshitsugu2Professor Emeritus,University of Tokyo,Tokyo,.JapanSearch for other works by this author on:T Okubo,T Okubo3Academic vice-president and professor,Sophia University,Tokyo,.JapanSearch for other works by this author on:T Aoki,T Aoki4Nuclear Power Engineering Test Center,Tokyo,.JapanSearch for other works by this author on:T Hattori,T Hattori5The Tokyo Electric Power Co., Inc.,Tokyo,.JapanSearch for other works by this author on:T Fujibayashi,T Fujibayashi6Isogo Engineering Center, Toshiba Corp.,Yokohama,.JapanSearch for other works by this author on:M Inagaki,M Inagaki7Hitachi Research Laboratory, Hitachi, Ltd.,Hitachi,.JapanSearch for other works by this author on:K Murota,K Murota8Engineering Department,Japan Nuclear Fuel Co., Ltd.,Yokosuka,.JapanSearch for other works by this author on:T Kodama,T Kodama9Nuclear Materials Technology Department,Sumitomo Metal Industries, Ltd.,Tokyo,.JapanSearch for other works by this author on:K AbeK Abe10Materials Research Laboratories, Kobe Steel, Ltd.,Kobe,.JapanSearch for other works by this author on:
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Corrosion Performance Ranking of Zircaloy-2 for BWR ApplicationsByP Rudling,P Rudling1Staff engineer,ABB ATOM AB, Fuel Division,S-7621 63, Västerås,.SwedenSearch for other works by this author on:AJ MachielsAJ Machiels2Program manager,Electric Power Research Institute,3412 Hillview Avenue, P.O. Box 10412,Palo Alto, CA 94303.Search for other works by this author on:
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Influence of Chemical Composition and Manufacturing Variables on Autoclave Corrosion of the ZircaloysByRA Graham,RA Graham1Senior research metallurgist, manager, process analysis, and senior research metallurgist, respectively,Teledyne Wah Chang Albany, P.O. Box 460,Albany, OR 97321.Search for other works by this author on:JP Tosdale,JP Tosdale1Senior research metallurgist, manager, process analysis, and senior research metallurgist, respectively,Teledyne Wah Chang Albany, P.O. Box 460,Albany, OR 97321.Search for other works by this author on:PT FindenPT Finden1Senior research metallurgist, manager, process analysis, and senior research metallurgist, respectively,Teledyne Wah Chang Albany, P.O. Box 460,Albany, OR 97321.Search for other works by this author on:
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Effects of Alloying Element Distribution on the Nodular Corrosion of Zircaloy-2ByK OgataK Ogata1Senior researcher,Nippon Nuclear Fuel Development Company, Ltd.,2163 Oarai-machi Naritacho, Higashi-Ibaraki-gun, Ibaraki-ken 311-13,.JapanSearch for other works by this author on:
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Electron Microscopy Study of Oxide Films Formed on Zircaloy-2 in Superheated SteamByB-X ZhouB-X Zhou1Research fellow,Southwest Centre for Reactor Engineering Research and Design, P.O. Box 291-601,Chengdu,.The People's Republic of ChinaSearch for other works by this author on:
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Heterogeneous Scale Growth During Steam Corrosion of Zircaloy-4 and 500°CByD Charquet,D Charquet1Senior research engineer and assistant vice president, research and development, respectively,CEZUS,Avenue Paul Girod BP 33, 73400 Ugine,.FranceSearch for other works by this author on:R Tricot,R Tricot2Vice president, research and development,CEZUS-Tour Manhattan, Cedex 21,92087 Paris La Defense,.FranceSearch for other works by this author on:J-F WadierJ-F Wadier1Senior research engineer and assistant vice president, research and development, respectively,CEZUS,Avenue Paul Girod BP 33, 73400 Ugine,.FranceSearch for other works by this author on:
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Automatic System for Measuring the Zirconium Liner and Zircaloy-2 Thickness of Zirconium Liner TubesByM Honji,M Honji1Manager and engineers, respectively,Steel Tube Works, Sumitomo, Metal Industries, Ltd.,1, Nishino-cho, Higashi-Mukojima, Amagasaki 660,.JapanSearch for other works by this author on:T Sakamoto,T Sakamoto2Assistant manager, System Engineering Division,Sumitomo Metal Industries, Ltd.,1-3, Nishinagasu-Hondori, Amagasaki 660,.JapanSearch for other works by this author on:Y Morimoto,Y Morimoto1Manager and engineers, respectively,Steel Tube Works, Sumitomo, Metal Industries, Ltd.,1, Nishino-cho, Higashi-Mukojima, Amagasaki 660,.JapanSearch for other works by this author on:S HyodoS Hyodo1Manager and engineers, respectively,Steel Tube Works, Sumitomo, Metal Industries, Ltd.,1, Nishino-cho, Higashi-Mukojima, Amagasaki 660,.JapanSearch for other works by this author on:
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Solubility Limits and Formation of Intermetallic Precipitates in ZrSnFeCr AlloysByD Charquet,D Charquet1Senior research engineer, research engineer, and assistant vice-presidentof Research and Development, respectively,CEZUS, Centre de Recherche CEZUS,Avenue Paul Girod BP 33, 73400 Ugine,.FranceSearch for other works by this author on:R Hahn,R Hahn2Research engineer and section manager, respectively,Siemens,8520 Erlangen,.West GermanySearch for other works by this author on:E Ortlieb,E Ortlieb2Research engineer and section manager, respectively,Siemens,8520 Erlangen,.West GermanySearch for other works by this author on:J-P Gros,J-P Gros1Senior research engineer, research engineer, and assistant vice-presidentof Research and Development, respectively,CEZUS, Centre de Recherche CEZUS,Avenue Paul Girod BP 33, 73400 Ugine,.FranceSearch for other works by this author on:J-F WadierJ-F Wadier1Senior research engineer, research engineer, and assistant vice-presidentof Research and Development, respectively,CEZUS, Centre de Recherche CEZUS,Avenue Paul Girod BP 33, 73400 Ugine,.FranceSearch for other works by this author on:
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Direct Measurement of Matrix Composition in Zircaloy-4 by Atom Probe MicroanalysisByB Wadman,B Wadman1Department of Physics,Chalmers University of Technology,S-412 96 G#x00F6;teborg,.SwedenSearch for other works by this author on:H-O AndrénH-O Andrén1Department of Physics,Chalmers University of Technology,S-412 96 G#x00F6;teborg,.SwedenSearch for other works by this author on:
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Diffusion of 3D Transition Elements in α-Zr and Zirconium AlloysByGM Hood,GM Hood1Research scientist and research technologist, respectively, Advanced Materials Research Branch, Reactor Materials Branch, Reactor Materials Division,Chalk River Nuclear Laboratories,Chalk River, Ontario K0J 1J0,.CanadaSearch for other works by this author on:RJ SchultzRJ Schultz1Research scientist and research technologist, respectively, Advanced Materials Research Branch, Reactor Materials Branch, Reactor Materials Division,Chalk River Nuclear Laboratories,Chalk River, Ontario K0J 1J0,.CanadaSearch for other works by this author on:
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Beta-Quenched Zircaloy-4: Effects of Thermal Aging and Neutron IrradiationByWJS Yang,WJS Yang1Principal engineer,GE Knolls Atomic Power Laboratory,Schenectady, NY 123301.Search for other works by this author on:RB AdamsonRB Adamson2Manager,Fuel Materials Technology, GE Nuclear Energy, Vallecitos Nuclear Center,Pleasanton, CA 94566.Search for other works by this author on:
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Intermetallic Precipitates in Zirconium-Niobium AlloysByX Meng,X Meng1Ph.D. student and professor and department head, respectively, Department of Engineering Materials,University of Windsor,Windsor, Ontario,.CanadaN9B 3P4Search for other works by this author on:DO NorthwoodDO Northwood1Ph.D. student and professor and department head, respectively, Department of Engineering Materials,University of Windsor,Windsor, Ontario,.CanadaN9B 3P4Search for other works by this author on:
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Magnetic Study of ZircaloyByC Miyake,C Miyake1Associate professor and Master of Engineering candidate, respectively, Department of Nuclear Engineering,Faculty of Engineering, Osaka University,Suita, Osaka 565,.JapanSearch for other works by this author on:T TakamiyaT Takamiya1Associate professor and Master of Engineering candidate, respectively, Department of Nuclear Engineering,Faculty of Engineering, Osaka University,Suita, Osaka 565,.JapanSearch for other works by this author on:
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Oxidation Kinetics and Auger Microprobe Analysis of Some Oxidized Zirconium AlloysByRA PlocRA Ploc1Atomic Energy of Canada Limited, Chalk River Nuclear Laboratories,Chalk River, Ontario K0JU 1J0,.CanadaSearch for other works by this author on:
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Simulated Fuel Expansion Testing of Zircaloy TubingByJP Foster,JP Foster1Senior engineer,Research and Development Center, Westinghouse Electric Corporation,Pitts-burgh, PA 15235.Search for other works by this author on:RA LeasureRA Leasure2Senior engineer, Commercial Nuclear Fuel Division,Westinghouse Electric Corporation,Columbia, SC.Search for other works by this author on:
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Link Between Stress Corrosion and Corrosion-Fatigue Behavior of Zircaloy in an Iodine EnvironmentByI Schuster,I Schuster1Research engineer and head of laboratory, respectively,Commissariat à l'Energie Atomie, Centre d'Etudes Nucléaires de Grenoble,85X-38041 GrenobleCedex,.FranceSearch for other works by this author on:C LemaignanC Lemaignan1Research engineer and head of laboratory, respectively,Commissariat à l'Energie Atomie, Centre d'Etudes Nucléaires de Grenoble,85X-38041 GrenobleCedex,.FranceSearch for other works by this author on:
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Effects of Irradiation and Hydriding on the Mechanical Properties of Zircaloy-4 at High FluenceByAM GardeAM Garde1Consulting engineer,Nuclear Fuel Product Development, Combustion Engineering,1000 Prospect Hill Rd., Windsor, CT 06095.Search for other works by this author on:
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Applications of Crystallographic Textures of Zirconium Alloys in the Nuclear IndustryByKL MurtyKL Murty1Professor,North Carolina State University, P.O. Box 7909,Raleigh, NC 27695-7909.Search for other works by this author on:
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Stress Versus Strain Rate Characteristics of Zircaloy Cladding Tubes Subjected to Various Deformation PathsByH Suzuki,H Suzuki1Research assistant and professor, respectively, Department of Mechanical Engineering,Sophia University,7-1 Kio-cho, Chiyoda-ku, Tokyo 102,.JapanSearch for other works by this author on:T OkuboT Okubo1Research assistant and professor, respectively, Department of Mechanical Engineering,Sophia University,7-1 Kio-cho, Chiyoda-ku, Tokyo 102,.JapanSearch for other works by this author on:
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The Influence of Tin Content on the Thermal Creep of Zircaloy-4ByWA McInteer,WA McInteer1Group supervisor and section manager, respectively, Babcock & Wilcox, Research and Development Division,Lynchburg, VA 24506-1165.Search for other works by this author on:DL Baty,DL Baty1Group supervisor and section manager, respectively, Babcock & Wilcox, Research and Development Division,Lynchburg, VA 24506-1165.Search for other works by this author on:KO SteinKO Stein2Advisory engineer,B&W Fuel Company,Lynchburg, VA 24506-0935.Search for other works by this author on:
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Effects of High Neutron Fluences on Microstructure and Growth of Zircaloy-4ByF Garzarolli,F Garzarolli1Deputy director and section managers, respectively,Siemens AG, KWU-Group,D-8520 Erlangen,.West GermanySearch for other works by this author on:P Dewes,P Dewes1Deputy director and section managers, respectively,Siemens AG, KWU-Group,D-8520 Erlangen,.West GermanySearch for other works by this author on:G Maussner,G Maussner1Deputy director and section managers, respectively,Siemens AG, KWU-Group,D-8520 Erlangen,.West GermanySearch for other works by this author on:H-H BassoH-H Basso1Deputy director and section managers, respectively,Siemens AG, KWU-Group,D-8520 Erlangen,.West GermanySearch for other works by this author on:
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Accelerated Irradiation Growth of Zirconium AlloysByM Griffiths,M Griffiths1Metallurgists, Advanced Materials Research Branch,Chalk River Nuclear Laboratories,Chalk River, Ontario KOJ 1JO,.CanadaSearch for other works by this author on:RW Gilbert,RW Gilbert2Metallurgist, Fuel Channel Components Branch,Chalk River Nuclear Laboratories,Chalk River, Ontario KOJ 1JO,.CanadaSearch for other works by this author on:V FidlerisV Fidleris1Metallurgists, Advanced Materials Research Branch,Chalk River Nuclear Laboratories,Chalk River, Ontario KOJ 1JO,.CanadaSearch for other works by this author on:
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Creep Behavior of Zircaloy Cladding Under Variable ConditionsByY MatsuoY Matsuo1Senior researcher,Central Research Institute, Mitsubishi Metal Corporation,Omiya, Saitama, 330.JapanSearch for other works by this author on:
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Effects of Microstructural Factors on Irradiation Growth in Zirconium-Niobium AlloysByN Sadaoka,N Sadaoka1Researcher and senior researcher, respectively,Energy Research Laboratory, Hitachi Ltd.,1168 Moriyama-cho, Htachi, Ibaraki 316,.JapanSearch for other works by this author on:M FuseM Fuse1Researcher and senior researcher, respectively,Energy Research Laboratory, Hitachi Ltd.,1168 Moriyama-cho, Htachi, Ibaraki 316,.JapanSearch for other works by this author on:
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The Effect of Temperature on the Irradiation Growth of Cold-Worked Zr-2.5 NbByRA Holt,RA Holt1Unit head of Deformation Mechanisms and supervising engineer, Materials Integrity Section, respectively, Ontario Hydro Research Division,800 Kipling Ave., Toronto, Ontario M8Z 5S4,.CanadaSearch for other works by this author on:RG FleckRG Fleck1Unit head of Deformation Mechanisms and supervising engineer, Materials Integrity Section, respectively, Ontario Hydro Research Division,800 Kipling Ave., Toronto, Ontario M8Z 5S4,.CanadaSearch for other works by this author on:
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© 1989
ASTM International
