Zirconium in the Nuclear Industry
The Fourth International Conference on Zirconium in the Nuclear Industry was held 26-29 June 1978, in Stratford-upon-Avon, England. This conference was sponsored by the American Society for Testing and Materials (ASTM) Committee B10 on Refractory Metals and Alloys in cooperation with the American Nuclear Society, the British Nuclear Energy Society, and The Metals Society (U.K).. The program was planned by representatives of ASTM Subcommittee B10.02 on Zirconium and Hafnium and K. G. Sumner of British Nuclear Fuels, Ltd. J. H. Schemel, Sandvik Special Metals Corp., and K. G. Sumner, BNFL, served as the conference co-chairmen, T. P. Papazoglou, The Babcock & Wilcox Company, as editorial chairman, and H. M. Cobb, ASTM Staff, as conference coordinator.
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Table of Contents
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IntroductionByTP PapazoglouTP Papazoglou1The Babcock & Wilcox Company,Lynchburg, Va. 24505;editorial chairman.Search for other works by this author on:
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Zirconium Technology—Twenty Years of EvolutionByB LustmanB Lustman1Manager,Fuel Development, Bettis Atomic Power Laboratory, Westinghouse Electric Corporation,West Mifflin, Pa. 15122.Search for other works by this author on:
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Zircaloy Performance in Light-Water ReactorsByJTA Roberts,JTA Roberts1Program managers, Nuclear Systems and Materials, Nuclear Power Division,Electric Power Research Institute, Inc.,Palo Alto, Calif. 94303.Search for other works by this author on:FE GelhausFE Gelhaus1Program managers, Nuclear Systems and Materials, Nuclear Power Division,Electric Power Research Institute, Inc.,Palo Alto, Calif. 94303.Search for other works by this author on:
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Effect of Material and Environmental Variables on Localized Corrosion of Zirconium AlloysByL Lunde,L Lunde1Metallurgist and head of metallurgy division, respectively,Institutt for atomenergi,Kjeller,.NorwaySearch for other works by this author on:K VidemK Videm1Metallurgist and head of metallurgy division, respectively,Institutt for atomenergi,Kjeller,.NorwaySearch for other works by this author on:
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Ductility of Zircaloy Canning Tubes in Relation to Stress Ratio in Biaxial TestingByT Andersson,T Andersson1Research metallurgists,Sandvik AB,Sandviken,.SwedenSearch for other works by this author on:A WilsonA Wilson1Research metallurgists,Sandvik AB,Sandviken,.SwedenSearch for other works by this author on:
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Localized Ductility Method for Evaluating Zircaloy-2 CladdingByLF CoffinLF Coffin1Mechanical engineer,Corporate Research and Development, General Electric Co.,Schenectady, New York.Search for other works by this author on:
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Review of Corrosion and Dimensional Behavior of Zircaloy under Water Reactor ConditionsByF Garzarolli,F Garzarolli1Senior scientific officer and scientific officer, Nuclear Fuel Division, R.a.D. Laboratory, and department manager, Reactor Division, Materials Laboratories, respectively,Kraftwerk Union AG,D-8520 Erlangen,.GermanySearch for other works by this author on:R Manzel,R Manzel1Senior scientific officer and scientific officer, Nuclear Fuel Division, R.a.D. Laboratory, and department manager, Reactor Division, Materials Laboratories, respectively,Kraftwerk Union AG,D-8520 Erlangen,.GermanySearch for other works by this author on:S Reschke,S Reschke2Plant manager,Nuklear Rohrgesellschaft,D-4100 Duisburg,.GermanySearch for other works by this author on:E TenckhoffE Tenckhoff1Senior scientific officer and scientific officer, Nuclear Fuel Division, R.a.D. Laboratory, and department manager, Reactor Division, Materials Laboratories, respectively,Kraftwerk Union AG,D-8520 Erlangen,.GermanySearch for other works by this author on:
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Further Evidence of Zircaloy Corrosion in Fuel Elements Irradiated in a Steam Generating Heavy Water ReactorByR Sumerling,R Sumerling1Senior assessor, Water Reactor Fuel Examination, section leader, Mechanical Properties and Corrosion, and section leader, Water Reactor Fuel Examination, respectively,United Kingdom Atomic Energy Authority, Windscale Nuclear Laboratories,Sellafield, Seascale, Cumbria C A20 1PF,.EnglandSearch for other works by this author on:A Garlick,A Garlick1Senior assessor, Water Reactor Fuel Examination, section leader, Mechanical Properties and Corrosion, and section leader, Water Reactor Fuel Examination, respectively,United Kingdom Atomic Energy Authority, Windscale Nuclear Laboratories,Sellafield, Seascale, Cumbria C A20 1PF,.EnglandSearch for other works by this author on:A Stuttard,A Stuttard1Senior assessor, Water Reactor Fuel Examination, section leader, Mechanical Properties and Corrosion, and section leader, Water Reactor Fuel Examination, respectively,United Kingdom Atomic Energy Authority, Windscale Nuclear Laboratories,Sellafield, Seascale, Cumbria C A20 1PF,.EnglandSearch for other works by this author on:JM Hartog,JM Hartog2Research manager and section leader, Chemical Technology Group, respectively,United Kingdom Atomic Energy Authority, Springfields Nuclear Laboratories,Salwick, Preston, PR4 ORR,.EnglandSearch for other works by this author on:FW Trowse,FW Trowse2Research manager and section leader, Chemical Technology Group, respectively,United Kingdom Atomic Energy Authority, Springfields Nuclear Laboratories,Salwick, Preston, PR4 ORR,.EnglandSearch for other works by this author on:P SimsP Sims3Physicist,Technology Branch, United Kingdom Atomic Energy Authority, Atomic Energy Establishment,Winfrith, Wool, Dorset, DT2 8DH,.EnglandSearch for other works by this author on:
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Performance of Irradiated Copper and Zirconium Barrier-Modified Zircaloy Cladding Under Simulated Pellet-Cladding Interaction ConditionsByDS Tomalin,DS Tomalin1Metallurgist, Metallurgy Laboratory, General Electric Corporate Research and Development; and manager, Core Materials Testing, General Electric Nuclear Technology Department; respectively,Vallecitos Nuclear Center,Pleasanton, Calif. 94566.Search for other works by this author on:RB Adamson,RB Adamson1Metallurgist, Metallurgy Laboratory, General Electric Corporate Research and Development; and manager, Core Materials Testing, General Electric Nuclear Technology Department; respectively,Vallecitos Nuclear Center,Pleasanton, Calif. 94566.Search for other works by this author on:RP Gangloff>RP Gangloff>2Metallurgist,Corporate Research and Development Center,Schenectady, N.Y.Search for other works by this author on:
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A Survey of the Chemical Environments for Activity in the Embrittlement of Zircaloy-2ByWT Grubb,WT Grubb1Research chemists,General Electric Corporate Research and Development,Schenectady, N.Y., 12301.Search for other works by this author on:MH Morgan, IIIMH Morgan, III1Research chemists,General Electric Corporate Research and Development,Schenectady, N.Y., 12301.Search for other works by this author on:
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Effect of Irradiation on the Strength, Ductility, and Defect Sensitivity of Fully Recrystallized Zircaloy TubeByK Pettersson,K Pettersson1Section head, Cladding Materials, Department for Nuclear Fuels and Core Materials,Studsvik, Energiteknik AB, Fach,S-61182, Nykoping,.SwedenSearch for other works by this author on:G Vesterlund,G Vesterlund2Specialist,Fuel Engineering, AB ASEA-ATOM, Box 53,S-72104, Västerås,.SwedenSearch for other works by this author on:T AnderssonT Andersson3Research metallurgist,High Temperature Materials, Sandvik AB, Fack,S-81101 Sandviken,.SwedenSearch for other works by this author on:
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Primary Creep of Zircaloy-2 Under IrradiationByV FidlerisV Fidleris1Senior research officer,Atomic Energy of Canada Limited, Chalk River Nuclear Laboratories,Chalk River, Ontario,.CanadaSearch for other works by this author on:
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Analysis of Irradiation Growth and Multiaxial Deformation Behavior of Nuclear Fuel CladdingByGS Clevinger,GS Clevinger1Group supervisor, senior engineer, and senior research engineerrespectively,Nuclear Metallurgy, The Babcock and Wilcox Company, Lynchburg Research Center,Lynchburg, Va.Search for other works by this author on:BL Adams,BL Adams1Group supervisor, senior engineer, and senior research engineerrespectively,Nuclear Metallurgy, The Babcock and Wilcox Company, Lynchburg Research Center,Lynchburg, Va.Search for other works by this author on:KL MurtyKL Murty1Group supervisor, senior engineer, and senior research engineerrespectively,Nuclear Metallurgy, The Babcock and Wilcox Company, Lynchburg Research Center,Lynchburg, Va.Search for other works by this author on:
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Analysis of Pressurized Water Reactor Fuel Pin Length ChangesByJE Harbottle,JE Harbottle1Research officers,Berkeley Nuclear Laboratories,Berkeley, Gloucestershire,.United KingdomSearch for other works by this author on:RM CornellRM Cornell1Research officers,Berkeley Nuclear Laboratories,Berkeley, Gloucestershire,.United KingdomSearch for other works by this author on:
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Irradiation Growth in Cold-Worked Zircaloy-2ByRA Murgatroyd,RA Murgatroyd1Section leader and research physicist, respectively,Risley Nuclear Power Development Laboratories, United Kingdom Atomic Energy Authority,Risley,.United KingdomSearch for other works by this author on:A RogersonA Rogerson1Section leader and research physicist, respectively,Risley Nuclear Power Development Laboratories, United Kingdom Atomic Energy Authority,Risley,.United KingdomSearch for other works by this author on:
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Stress Corrosion Crack Initiation and Growth and Formation of Pellet-Clad Interaction DefectsByK Videm,K Videm1Head and metallurgist, respectively, Metallurgy Division,Institutt for atomenergi,Kjeller,.NorwaySearch for other works by this author on:L LundeL Lunde1Head and metallurgist, respectively, Metallurgy Division,Institutt for atomenergi,Kjeller,.NorwaySearch for other works by this author on:
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Out-of-Pile Testing of Iodine Stress Corrosion Cracking in Zircaloy Tubing in Relation to the Pellet-Cladding Interaction PhenomenonByM Peehs,M Peehs1Physicists and engineer, respectively,Research and Development Reactor Group, Kraftwerk Union AG,Erlangen,.GermanySearch for other works by this author on:H Stehle,H Stehle1Physicists and engineer, respectively,Research and Development Reactor Group, Kraftwerk Union AG,Erlangen,.GermanySearch for other works by this author on:E SteinbergE Steinberg1Physicists and engineer, respectively,Research and Development Reactor Group, Kraftwerk Union AG,Erlangen,.GermanySearch for other works by this author on:
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Iodine-Induced Stress Corrosion Cracking of Fixed Deflection Stressed Slotted Rings of Zircaloy Fuel CladdingByR Sejnoha,R Sejnoha1Section manager,Research and Development, Combustion Engineering-Superheater Limited,Moncton, N.B.,.CanadaSearch for other works by this author on:JC WoodJC Wood2Group leader,Mechanistic Studies, Fuel Engineering Branch, Atomic Energy of Canada Limited, Chalk River Nuclear Laboratories,Chalk River, Ontario,.CanadaSearch for other works by this author on:
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A Stress Corrosion Cracking Model for Pellet-Cladding Interaction Failures in Light-Water Reactor Fuel RodsByJTA Roberts,JTA Roberts1Program manager and Project manager, respectively,Electric Power Research Institute,Palo Alto, Calif. 94303.Search for other works by this author on:RL Jones,RL Jones1Program manager and Project manager, respectively,Electric Power Research Institute,Palo Alto, Calif. 94303.Search for other works by this author on:D Cubicciotti,D Cubicciotti2Senior scientist,Stanford Research Institute,Menlo Park, Calif. 94025.Search for other works by this author on:AK Miller,AK Miller3Assistant professor,Stanford University,Stanford Calif.Search for other works by this author on:HF Wachob,HF Wachob4Research scientist,NASA/Ames Research Center,Moffet Field, Calif. 94035.Search for other works by this author on:E Smith,E Smith5Consultant,Failure Analysis Associates,Palo Alto, Calif. 94305.Search for other works by this author on:FL YaggeeFL Yaggee6Associate metallurgist,Argonne National Laboratory,Argonne, Ill.Search for other works by this author on:
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Hydride Cracks as Initiators for Stress Corrosion Cracking of ZircaloysByB CoxB Cox1Branch head,Materials Science Branch, Atomic Energy of Canada Limited, Chalk River Nuclear Laboratories,Chalk River, Ontario,.CanadaSearch for other works by this author on:
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Predicting High-Temperature Transient Deformation from Microstructural ModelsByHE Sills,HE Sills1Mathematician and metallurgist, respectively,Atomic Energy of Canada Limited, Chalk River Nuclear Laboratories,Chalk River, Ontario,.CanadaSearch for other works by this author on:RA HoltRA Holt1Mathematician and metallurgist, respectively,Atomic Energy of Canada Limited, Chalk River Nuclear Laboratories,Chalk River, Ontario,.CanadaSearch for other works by this author on:
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A Microstructure-Based Constitutive Relation for Dilute Alloys of α-ZirconiumByCS Hartley,CS Hartley1Materials Science and Engineering Department,University of Florida,Gainesville Fla. 32611.Search for other works by this author on:J-J Lee,J-J Lee1Materials Science and Engineering Department,University of Florida,Gainesville Fla. 32611.Search for other works by this author on:A Garde,A Garde2Materials Science Division,Agronne National Laboratory,Argonne, Ill. 60439.Search for other works by this author on:HM Chung,HM Chung2Materials Science Division,Agronne National Laboratory,Argonne, Ill. 60439.Search for other works by this author on:TF KassnerTF Kassner2Materials Science Division,Agronne National Laboratory,Argonne, Ill. 60439.Search for other works by this author on:
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A Comparison of Experimental Cladding Microstructure Resulting from Uranium Oxide-Zircaloy Interaction with a Diffusional Assessment of Oxygen Transport for a Coupled Two-Media ProblemByAW Cronenberg,AW Cronenberg1Senior scientist,EG&G Idaho,Idaho Falls, Idaho 83401.Search for other works by this author on:MS El-GenkMS El-Genk2Nuclear engineer, Chemical and Nuclear Engineering Department,University of New Mexico,Albuquerque, N. Mex. 87131.Search for other works by this author on:
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Advances in Understanding and Predicting Inelastic Deformation in ZircaloyByS Oldberg, Jr,S Oldberg, Jr1Project manager,Electric Power Research Institute,Palo Alto, Calif. 94304.Search for other works by this author on:AK Miller,AK Miller2Assistant professor,Stanford University,Stanford, Calif.Search for other works by this author on:GE LucasGE Lucas3Assistant professor,University of California,Santa Barbara, Calif.Search for other works by this author on:
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Zirconium Cladding Deformation in a Steam Environment with Transient HeatingByRH Chapman,RH Chapman1Manager, project leader, and project engineer, respectively,Multirod Burst Test Program, Engineering Technology Division, Oak Ridge National Laboratory,Oak Ridge, Tennessee 37830.Search for other works by this author on:JL Crowley,JL Crowley1Manager, project leader, and project engineer, respectively,Multirod Burst Test Program, Engineering Technology Division, Oak Ridge National Laboratory,Oak Ridge, Tennessee 37830.Search for other works by this author on:AW Longest,AW Longest1Manager, project leader, and project engineer, respectively,Multirod Burst Test Program, Engineering Technology Division, Oak Ridge National Laboratory,Oak Ridge, Tennessee 37830.Search for other works by this author on:G HofmannG Hofmann2Guest scientist,Oak Ridge National Laboratory, August 1975 to August 1977, fromKarlsruhe Nuclear Research Center,Karlsruhe,.GermanySearch for other works by this author on:
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Influence of Iodine on the Strain and Rupture Behavior of Zircaloy-4 Cladding Tubes at High TemperaturesByP HofmannP Hofmann1Senior scientist and metallurgist,Institut fur Material- und Festkorperforschung, Projekt Nukleare Sicherheit,7500 Karlsruhe, Postfach 3640,.Federal Republic of GermanySearch for other works by this author on:
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Studies on Zircaloy Fuel Clad Ballooning in a Loss-of-Coolant Accident—Results of Burst Tests with Indirectly Heated Fuel Rod SimulatorsByF Erbacher,F Erbacher1Section leader and engineers, respectively,Kernforschungszentrum Karlsruhe, Institut für Reaktorbauelemente, Projekt Nukleare Sicherheit,7500 Karlsruhe, Postfach 3640,.Federal Republic of GermanySearch for other works by this author on:HJ Neitzel,HJ Neitzel1Section leader and engineers, respectively,Kernforschungszentrum Karlsruhe, Institut für Reaktorbauelemente, Projekt Nukleare Sicherheit,7500 Karlsruhe, Postfach 3640,.Federal Republic of GermanySearch for other works by this author on:K WiehrK Wiehr1Section leader and engineers, respectively,Kernforschungszentrum Karlsruhe, Institut für Reaktorbauelemente, Projekt Nukleare Sicherheit,7500 Karlsruhe, Postfach 3640,.Federal Republic of GermanySearch for other works by this author on:
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Effect of β-Phase Heat Treatment on the Subsequent α-Phase Ballooning Behavior of Zircaloy-4 Fuel SheathsByCEL Hunt,CEL Hunt1Research engineer and technician, respectively,Fuel Engineering Branch, Atomic Energy of Canada Limited, Chalk River Nuclear Laboratories, Fuel Engineering Branch,Chalk River, Ontario,.CanadaSearch for other works by this author on:WG NewellWG Newell1Research engineer and technician, respectively,Fuel Engineering Branch, Atomic Energy of Canada Limited, Chalk River Nuclear Laboratories, Fuel Engineering Branch,Chalk River, Ontario,.CanadaSearch for other works by this author on:
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Tube-Burst Response of Irradiated Zircaloy Spent-Fuel CladdingByAA Bauer,AA Bauer1Research leader, research scientist, and research scientist, respectively,Battelle's Columbus Laboratories,Columbus, Ohio 43201.Search for other works by this author on:LM Lowry,LM Lowry1Research leader, research scientist, and research scientist, respectively,Battelle's Columbus Laboratories,Columbus, Ohio 43201.Search for other works by this author on:WJ GallagherWJ Gallagher1Research leader, research scientist, and research scientist, respectively,Battelle's Columbus Laboratories,Columbus, Ohio 43201.Search for other works by this author on:
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A Proposed Criterion for the Oxygen Embrittlement of Zircaloy-4 Fuel CladdingByA SawatzkyA Sawatzky1Senior research officer,Materials and Component Development Branch, Whiteshell Nuclear Research Establishment,Pinawa, Manitoba,.CanadaSearch for other works by this author on:
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Effect of Oxygen on the Deformation of Zircaloy-2 at Elevated TemperaturesByAS Rizkalla,AS Rizkalla1Combustion Engineering Superheater Ltd.,Sherbrooke, Quebec,.Canada, JIH-5J9Search for other works by this author on:RA Holt,RA Holt2Atomic Energy of Canada Limited,Chalk River, Ontario,.Canada, KOJ-1JOSearch for other works by this author on:JJ JonasJJ Jonas3Professor of mechanical metallurgy, Department of Mining and Metallurgical Engineering,McGill University,Montreal, Quebec,.Canada, H3A-2A7Search for other works by this author on:
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Evaluation Models of Zircaloy Oxidation in Light of Recent ExperimentsByH Ocken,H Ocken1Project manager,Electric Power Research Institute,Palo Alto, Calif. 94304.Search for other works by this author on:RR Biederman,RR Biederman2Professor,Worcester Polytechnic Institute,Worcester, Mass. 01609.Search for other works by this author on:CR Hann,CR Hann3Manager, Fuels Design and Development, and staff scientist, respectively,Battelle, Pacific Northwest Laboratories,Richland, Wash. 99352.Search for other works by this author on:RE WestermanRE Westerman3Manager, Fuels Design and Development, and staff scientist, respectively,Battelle, Pacific Northwest Laboratories,Richland, Wash. 99352.Search for other works by this author on:
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Chemical Interaction Between Uranium Oxide and Zircaloy-4 in the Temperature Range Between 900 and 1500°CByP Hofmann,P Hofmann1Senior scientists and metallurgists,Institut für Material- and Festkorperforschung, Projekt Nukleare Sicherheit, Kernforschungszentrum Karlsruhe,7500 Karlsruhe, Postfach 3640,.Federal Republic of GermanySearch for other works by this author on:C PolitisC Politis1Senior scientists and metallurgists,Institut für Material- and Festkorperforschung, Projekt Nukleare Sicherheit, Kernforschungszentrum Karlsruhe,7500 Karlsruhe, Postfach 3640,.Federal Republic of GermanySearch for other works by this author on:
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Interaction of Oxidation and Creep in Zircaloy-2ByB Burton,B Burton1Research officers, Central Electricity Generating Board,Berkeley Nuclear Laboratories,Berkeley, Gloucestershire,.United KingdomSearch for other works by this author on:AT Donaldson,AT Donaldson1Research officers, Central Electricity Generating Board,Berkeley Nuclear Laboratories,Berkeley, Gloucestershire,.United KingdomSearch for other works by this author on:GL ReynoldsGL Reynolds1Research officers, Central Electricity Generating Board,Berkeley Nuclear Laboratories,Berkeley, Gloucestershire,.United KingdomSearch for other works by this author on:
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Embrittlement of Zircaloy-Clad Fuel Rods Irradiated Under Film Boiling ConditionsByRR Hobbins,RR Hobbins1Supervisor, Fuel Evaluation Section, Fuels Engineering Branch, senior metallurgist, Fuels Engineering Branch, metallurgist, Fuels Engineering Branch, supervisor, PCM, RIA and FPDS Section, PBF Experiment Specification and Analysis Branch, and manager, LWR Fuel Research Division, respectively,EG & G Idaho, Inc.,Idaho Falls, Idaho 83401.Search for other works by this author on:SL Seiffert,SL Seiffert1Supervisor, Fuel Evaluation Section, Fuels Engineering Branch, senior metallurgist, Fuels Engineering Branch, metallurgist, Fuels Engineering Branch, supervisor, PCM, RIA and FPDS Section, PBF Experiment Specification and Analysis Branch, and manager, LWR Fuel Research Division, respectively,EG & G Idaho, Inc.,Idaho Falls, Idaho 83401.Search for other works by this author on:SA Ploger,SA Ploger1Supervisor, Fuel Evaluation Section, Fuels Engineering Branch, senior metallurgist, Fuels Engineering Branch, metallurgist, Fuels Engineering Branch, supervisor, PCM, RIA and FPDS Section, PBF Experiment Specification and Analysis Branch, and manager, LWR Fuel Research Division, respectively,EG & G Idaho, Inc.,Idaho Falls, Idaho 83401.Search for other works by this author on:AS Mehner,AS Mehner1Supervisor, Fuel Evaluation Section, Fuels Engineering Branch, senior metallurgist, Fuels Engineering Branch, metallurgist, Fuels Engineering Branch, supervisor, PCM, RIA and FPDS Section, PBF Experiment Specification and Analysis Branch, and manager, LWR Fuel Research Division, respectively,EG & G Idaho, Inc.,Idaho Falls, Idaho 83401.Search for other works by this author on:PE MacDonaldPE MacDonald1Supervisor, Fuel Evaluation Section, Fuels Engineering Branch, senior metallurgist, Fuels Engineering Branch, metallurgist, Fuels Engineering Branch, supervisor, PCM, RIA and FPDS Section, PBF Experiment Specification and Analysis Branch, and manager, LWR Fuel Research Division, respectively,EG & G Idaho, Inc.,Idaho Falls, Idaho 83401.Search for other works by this author on:
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Development of an Oxygen Embrittlement Criterion for Zircaloy Cladding Applicable to Loss-of-Coolant Accident Conditions in Light-Water ReactorsByHM Chung,HM Chung1Metallurgists and senior metallurgist, respectively, Materials Science Division,Argonne National Laboratory,Argonne, Illinois, 60439.Search for other works by this author on:AM Garde,AM Garde1Metallurgists and senior metallurgist, respectively, Materials Science Division,Argonne National Laboratory,Argonne, Illinois, 60439.Search for other works by this author on:TF KassnerTF Kassner1Metallurgists and senior metallurgist, respectively, Materials Science Division,Argonne National Laboratory,Argonne, Illinois, 60439.Search for other works by this author on: