Skip Nav Destination
100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959 : ASTM International, 1991.
ASTM Selected Technical Papers
Zirconium in the Nuclear Industry: Ninth International Symposium
By
CM Eucken,
CM Eucken
1
Teledyne Wah Chang Albany
?Albany, OR 97321 Symposium Chairman and STP Editor
Search for other works by this author on:
AM Garde
AM Garde
2
ABB Combustion Engineering Nuclear Power
, Windsor, CT 06095 Symposium Editorial Chairman and STP Editor
Search for other works by this author on:
ISBN-10:
0-8031-1463-X
ISBN:
978-0-8031-1463-0
No. of Pages:
807
Publisher:
ASTM International
Publication date:
1991
Description
36 papers from the most significant body of technical literature on zirconium alloy properties. Sections include: Fabrication, Mechanical Properties, and Corrosion.
Eucken, C, & Garde, A.
Zirconium in the Nuclear Industry: Ninth International Symposium. ISBN-10: 0-8031-1463-X
ISBN: 978-0-8031-1463-0
No. of Pages: 807
ISBN (electronic): 978-0-8031-5177-2
Publisher: ASTM International
Published: 1991
Download citation file:
Table of Contents
-
Zirconium-Alloy Corrosion: A Review Based on an International Atomic Energy Agency (IAEA) MeetingByDG Franklin,DG Franklin1Manager,Cladding Development, Westinghouse Bettis Atomic Power Laboratory,West Mifflin, PA 15122.Search for other works by this author on:PM LangPM Lang2Program Manager,Extended Burnup, U.S. Department of Energy,Washington, DC 20585.Search for other works by this author on:
-
Deformability of Zirconium-Lined Cladding Tube in Cold PilgeringByH Abe,H Abe1Steel Tube Works, Sumitomo Metal Industries, Ltd.,Amagasaki, Hyogo, 660,.JapanSearch for other works by this author on:H Tarui,H Tarui1Steel Tube Works, Sumitomo Metal Industries, Ltd.,Amagasaki, Hyogo, 660,.JapanSearch for other works by this author on:T Kobayashi,T Kobayashi1Steel Tube Works, Sumitomo Metal Industries, Ltd.,Amagasaki, Hyogo, 660,.JapanSearch for other works by this author on:M Honji,M Honji1Steel Tube Works, Sumitomo Metal Industries, Ltd.,Amagasaki, Hyogo, 660,.JapanSearch for other works by this author on:T KonishiT Konishi1Steel Tube Works, Sumitomo Metal Industries, Ltd.,Amagasaki, Hyogo, 660,.JapanSearch for other works by this author on:
-
Processing Map and Hot Working Characteristics of Zircaloy-2ByJK Chakravartty,JK Chakravartty1Metallurgy Division,Bhabha Atomic Research Centre,Bombay 400 085,.IndiaSearch for other works by this author on:YVRK Prasad,YVRK Prasad2Department of Metallurgy,Indian Institute of Science,Bangalore 560 012,.IndiaSearch for other works by this author on:MK AsundiMK Asundi3Naval Chemical and Metallurgical Laboratory,Tiger Gate, Bombay,.IndiaSearch for other works by this author on:
-
Establishing Statistical Models of Manufacturing Parameters: Zircaloy-4 Cladding Tube PropertiesByJ-F DeshayesJ-F Deshayes1Zircotube,44560 Paimboeuf,.FranceSearch for other works by this author on:
-
Texture Control in Zircaloy Tubing Through ProcessingByCS Cook,CS Cook1Westinghouse Science and Technology Center,Pittsburgh, PA 15235.Search for other works by this author on:GP Sabol,GP Sabol2Westinghouse Commercial Nuclear Fuel Division,Pittsburgh, PA 15230.Search for other works by this author on:KR Sekera,KR Sekera3Westinghouse Specialty Metals Plant,Blairsville, PA 15717.Search for other works by this author on:SN RandallSN Randall4Westinghouse Specialty Metals Plant(retired),Blairsville, PA 15717.Search for other works by this author on:
-
Fracture Toughness Evaluation of Heat-Treated Zr-2.5Nb Pressure TubesByT Asada,T Asada1Power Reactor and Nuclear Fuel Development Corporation,Oarai-machi, Ibaraki,.JapanSearch for other works by this author on:H Kimoto,H Kimoto2Mechanical Engineering Research Laboratory, Hitachi, Ltd.,Tsuchiura,.JapanSearch for other works by this author on:N Chiba,N Chiba2Mechanical Engineering Research Laboratory, Hitachi, Ltd.,Tsuchiura,.JapanSearch for other works by this author on:Y KasaiY Kasai1Power Reactor and Nuclear Fuel Development Corporation,Oarai-machi, Ibaraki,.JapanSearch for other works by this author on:
-
Effect of Tensile Deformation on Crystallographic Texture in Zircaloy SheetByST Mahmood,ST Mahmood1North Carolina State University,Raleigh, NC 27695-7909.Search for other works by this author on:KL MurtyKL Murty1North Carolina State University,Raleigh, NC 27695-7909.Search for other works by this author on:
-
Correlation of Microstructure and Mechanical Properties of Zr-Sn AlloysBySL Wadekar,SL Wadekar1Metallurgy Division,Bhaba Atomic Research Centre,Bombay 400 085,.IndiaSearch for other works by this author on:S Banerjee,S Banerjee1Metallurgy Division,Bhaba Atomic Research Centre,Bombay 400 085,.IndiaSearch for other works by this author on:VV Raman,VV Raman1Metallurgy Division,Bhaba Atomic Research Centre,Bombay 400 085,.IndiaSearch for other works by this author on:MK AsundiMK Asundi2Naval Chemical and Metallurgical Laboratory,Bombay 400 023,.IndiaSearch for other works by this author on:
-
Microstructure of Zr-2.5Nb Alloy Pressure TubingByDO Northwood,DO Northwood1Professor of Engineering Materials and Ph.D. student, respectively,Engineering Materials Group, University of Windsor,Windsor, Ontario,.CanadaN9B 3P4Search for other works by this author on:X Meng-Burany,X Meng-Burany1Professor of Engineering Materials and Ph.D. student, respectively,Engineering Materials Group, University of Windsor,Windsor, Ontario,.CanadaN9B 3P42Post-Doctoral Research Fellow, Department of Physics,Simon Fraser University,Burnaby, B.C.,.CanadaV5A 1S6Search for other works by this author on:BD WarrBD Warr3Scientist, Corrosion and Tritium Technology Section, Metallurgical Research Department,Ontario Hydro,Toronto, Ontario,.CanadaM8Z 5S4Search for other works by this author on:
-
Growth in Zircaloy-4 Fuel Clad Arising from Oxidation at Temperatures in the Range 623 to 723 KByAT DonaldsonAT Donaldson1Research Officer,Nuclear Electric plc,Berkeley, Gloucestershire, GL13 9PB,.United KingdomSearch for other works by this author on:
-
Effects of Recrystallization and Neutron Irradiation on Creep Anisotropy of Zircaloy CladdingByKL Murty,KL Murty1North Carolina State University,Raleigh, NC 27695.Search for other works by this author on:ST MahmoodST Mahmood1North Carolina State University,Raleigh, NC 27695.Search for other works by this author on:
-
The Contribution of Irradiation Growth to Pressure Tube DeformationByRA Holt,RA Holt1Ontario Hydro Research Division, Metallurgical Research Department,Toronto, Ontario,. The first author is now atCanadaM8Z 5S4Atomic Energy of Canada Limited, Chalk River Nuclear Laboratories, Reactor Materials Division,Chalk River, Ontario,.CanadaK0J 1J0Search for other works by this author on:RG FleckRG Fleck1Ontario Hydro Research Division, Metallurgical Research Department,Toronto, Ontario,. The first author is now atCanadaM8Z 5S4Atomic Energy of Canada Limited, Chalk River Nuclear Laboratories, Reactor Materials Division,Chalk River, Ontario,.CanadaK0J 1J0Search for other works by this author on:
-
Fatigue Behavior of Neutron Irradiated Zircaloy-2 Fuel Cladding TubesByM Nakatsuka,M Nakatsuka1Nippon Nuclear Fuel Development Company, Ltd.,2163 Narita-cho, Oarai-machi, Higashi-ibaraki-gun, Ibaraki-pref.,.JapanSearch for other works by this author on:T Kubo,T Kubo1Nippon Nuclear Fuel Development Company, Ltd.,2163 Narita-cho, Oarai-machi, Higashi-ibaraki-gun, Ibaraki-pref.,.JapanSearch for other works by this author on:Y HayashiY Hayashi1Nippon Nuclear Fuel Development Company, Ltd.,2163 Narita-cho, Oarai-machi, Higashi-ibaraki-gun, Ibaraki-pref.,.JapanSearch for other works by this author on:
-
Fracture Toughness of Irradiated Zr-2.5Nb Pressure Tubes from CANDU ReactorsByCK Chow,CK Chow1AECL Research, Whiteshell Laboratories,Pinawa, Manitoba,.CanadaR0E 1L0Search for other works by this author on:CE Coleman,CE Coleman2AECL Research, Chalk River Laboratories,Chalk River, Ontario,.CanadaK0J 1J0Search for other works by this author on:RR Hosbons,RR Hosbons2AECL Research, Chalk River Laboratories,Chalk River, Ontario,.CanadaK0J 1J0Search for other works by this author on:PH Davies,PH Davies2AECL Research, Chalk River Laboratories,Chalk River, Ontario,.CanadaK0J 1J0Search for other works by this author on:M Griffiths,M Griffiths2AECL Research, Chalk River Laboratories,Chalk River, Ontario,.CanadaK0J 1J0Search for other works by this author on:R ChoubeyR Choubey1AECL Research, Whiteshell Laboratories,Pinawa, Manitoba,.CanadaR0E 1L0Search for other works by this author on:
-
Controlled Composition Zircaloy-2 Uniform Corrosion ResistanceByRA Graham,RA Graham1Manager, Process Engineering, and Manager, Process Development, respectively,Teledyne Wah Chang Albany,Albany, OR 97321.Search for other works by this author on:CM EuckenCM Eucken1Manager, Process Engineering, and Manager, Process Development, respectively,Teledyne Wah Chang Albany,Albany, OR 97321.Search for other works by this author on:
-
Influence of Alloy Composition and Processing on the Nodular Corrosion Resistance of Zircaloy-2ByER Bradley,ER Bradley1Sandvik Special Metals Corporation,Kennewick, WA 99336.Search for other works by this author on:JH Schemel,JH Schemel1Sandvik Special Metals Corporation,Kennewick, WA 99336.Search for other works by this author on:A-L NystömA-L Nystöm2AB Sandvik Steel,Sandviken,.SwedenSearch for other works by this author on:
-
Investigation of Nodular Corrosion Mechanism for Zircaloy ProductsByCT Wang,CT Wang1Teledyne Wah Chang Albany,Albany, OR 97321.Search for other works by this author on:CM Eucken,CM Eucken1Teledyne Wah Chang Albany,Albany, OR 97321.Search for other works by this author on:RA GrahamRA Graham1Teledyne Wah Chang Albany,Albany, OR 97321.Search for other works by this author on:
-
Development of Highly Corrosion Resistant Zirconium-Base AlloysByT Isobe,T Isobe1Central Research Institute, Mitsubishi Metal Corporation,1-297 Kitabukuro-Cho, Omiya, Saitama,.Japan330Search for other works by this author on:Y MatsuoY Matsuo1Central Research Institute, Mitsubishi Metal Corporation,1-297 Kitabukuro-Cho, Omiya, Saitama,.Japan330Search for other works by this author on:
-
Effect of Alloying Elements on Uniform Corrosion Resistance of Zirconium-based Alloys in 360°C Water and 400°C SteamByM Harada,M Harada1Materials Research Laboratory, Kobe Steel Ltd.,1-3-18, Wakinohama-cho. Chuo-ku, Kobe City,.Japan, 651Search for other works by this author on:M Kimpara,M Kimpara1Materials Research Laboratory, Kobe Steel Ltd.,1-3-18, Wakinohama-cho. Chuo-ku, Kobe City,.Japan, 651Search for other works by this author on:K AbeK Abe1Materials Research Laboratory, Kobe Steel Ltd.,1-3-18, Wakinohama-cho. Chuo-ku, Kobe City,.Japan, 651Search for other works by this author on:
-
Oxide Growth Mechanism on Zirconium AlloysByF Garzarolli,F Garzarolli1Siemens, AG,D-8520 Erlangen,.GermanySearch for other works by this author on:H Seidel,H Seidel1Siemens, AG,D-8520 Erlangen,.GermanySearch for other works by this author on:R Tricot,R Tricot2CEZUS, Tour Manhattan, Cedex 21,92087 Paris la Defense,.FranceSearch for other works by this author on:JP GrosJP Gros3CEZUS, Centre de Recherches,Ugine,.FranceSearch for other works by this author on:
-
Raman Spectroscopy Study of the Tetragonal-to-monoclinic Transition in Zirconium Oxide Scales and Determination of Overall Oxygen Diffusion by Nuclear Microanalysis of O18ByJ Godlewski,J Godlewski1Thesis Student and Professor, respectively,Université de Compiègne, Division Matériaux.UA 849,CNRS,Compiegne,.FranceSearch for other works by this author on:JP Gros,JP Gros2Research Engineer and Research and Development Manager, respectively,CEZUS, Centre de Recherches,Ugine,.FranceSearch for other works by this author on:M Lambertin,M Lambertin1Thesis Student and Professor, respectively,Université de Compiègne, Division Matériaux.UA 849,CNRS,Compiegne,.FranceSearch for other works by this author on:JF Wadier,JF Wadier2Research Engineer and Research and Development Manager, respectively,CEZUS, Centre de Recherches,Ugine,.FranceSearch for other works by this author on:H WeidingerH Weidinger3Senior Director,Siemens A.G., KWU Group,Erlangen..GermanySearch for other works by this author on:
-
Effect of Alloying Elements in Zircaloy on Photo-Electrochemical Characteristics of Zirconium Oxide FilmsByM Inagaki,M Inagaki1Hitachi Research Laboratory,3-1-1 Saiwai-cho, Hitachi City, Ibaraki-Kenn, 317.JapanSearch for other works by this author on:M Kanno,M Kanno1Hitachi Research Laboratory,3-1-1 Saiwai-cho, Hitachi City, Ibaraki-Kenn, 317.JapanSearch for other works by this author on:H MakiH Maki2Hitachi Works, Hitachi Ltd.,3-1-1 Saiwai-cho, Hitachi City, Ibaraki-Kenn, 317.JapanSearch for other works by this author on:
-
Microanalysis of the Matrix and the Oxide-Metal Interface of Uniformly Corroded ZircaloyByB Wadman,B Wadman1Department of Physics,Chalmers University of Technology,S-412 96 Göteborg,.SwedenSearch for other works by this author on:H-O AndrénH-O Andrén1Department of Physics,Chalmers University of Technology,S-412 96 Göteborg,.SwedenSearch for other works by this author on:
-
Precipitate Behavior in Zircaloy-2 Oxide Films and Its Relevance to Corrosion ResistanceByT Kubo,T Kubo1Nippon Nuclear Fuel Development Co. Ltd.,2163 Narita-cho, Oarai-machi, Higashi-Ibaraki-gun., Ibaraki-ken,.JapanSearch for other works by this author on:M UnoM Uno1Nippon Nuclear Fuel Development Co. Ltd.,2163 Narita-cho, Oarai-machi, Higashi-Ibaraki-gun., Ibaraki-ken,.JapanSearch for other works by this author on:
-
Corrosion-Electrochemical Properties of Zirconium IntermetallicsByHG Weidinger,HG Weidinger1Siemens KWU AG,Erlangen,.GermanySearch for other works by this author on:G Cheliotis,G Cheliotis1Siemens KWU AG,Erlangen,.GermanySearch for other works by this author on:M Maguire,M Maguire2Teledyne Wah Chang,Albany, OR 97321.3Atomic Energy of Canada Ltd.,Chalk River, Ontario,.CanadaK0J 1J0Search for other works by this author on:T-L YauT-L Yau2Teledyne Wah Chang,Albany, OR 97321.Search for other works by this author on:
-
Comparison of Zircaloy Corrosion Models from the Evaluation of In-Reactor and Out-of-Pile Loop PerformanceByPh Billot,Ph Billot1Commissariat à l'Energie Atomique (CEA), CEN Cadarache,13108 St. Paul-lez-Durance,.FranceSearch for other works by this author on:A GiordanoA Giordano1Commissariat à l'Energie Atomique (CEA), CEN Cadarache,13108 St. Paul-lez-Durance,.FranceSearch for other works by this author on:
-
Enhancement of Aqueous Corrosion of Zircaloy-4 Due to Hydride Precipitation at the Metal-Oxide InterfaceByAM GardeAM Garde1ABB Combustion Engineering Nuclear Power,Windsor, CT 06095.Search for other works by this author on:
-
Corrosion of Zircaloy in the Presence of LiOHByRA Perkins,RA Perkins1SIEMENS Nuclear Power Corporation,Richland, WA 99352.Search for other works by this author on:RA BuschRA Busch1SIEMENS Nuclear Power Corporation,Richland, WA 99352.Search for other works by this author on:
-
Lithium Uptake and the Corrosion of Zirconium Alloys in Aqueous Lithium Hydroxide SolutionsByN RamasubramanianN Ramasubramanian1Research Officer,AECL Research, System Chemistry and Corrosion Branch, Chalk River Laboratories,Chalk River, Ontario K0J 1J0.CanadaSearch for other works by this author on:
-
Corrosion of Zircaloy-4 Pwr Fuel Cladding in Lithiated and Borated Water EnvironmentsByIL Bramwell,IL Bramwell1Risley Laboratories,Risley, Warrington, Cheshire,.EnglandSearch for other works by this author on:PD Parsons,PD Parsons1Risley Laboratories,Risley, Warrington, Cheshire,.EnglandSearch for other works by this author on:DR TiceDR Tice1Risley Laboratories,Risley, Warrington, Cheshire,.EnglandSearch for other works by this author on:
-
Effects Of LiOH on Pretransition Zirconium Oxide Films
-
Investigation of Variables That Influence Corrosion of Zirconium Alloys during IrradiationByVF Urbanic,VF Urbanic1AECL Research, Chalk River Laboratories,Chalk River, Ontario,.CanadaSearch for other works by this author on:R Choubey,R Choubey2AECL Research, Whiteshell Laboratories,Pinawa, Manitoba,.CanadaSearch for other works by this author on:CK ChowCK Chow2AECL Research, Whiteshell Laboratories,Pinawa, Manitoba,.CanadaSearch for other works by this author on:
-
Characteristics of Autoclave and In-Reactor Nodular Corrosion of ZircaloysByYH Jeong,YH Jeong1Korea Atomic Energy Research Institute,Daeduk-Danji, Choong-Nam,.Republic of KoreaSearch for other works by this author on:KS Rheem,KS Rheem1Korea Atomic Energy Research Institute,Daeduk-Danji, Choong-Nam,.Republic of KoreaSearch for other works by this author on:HM ChungHM Chung2Materials and Components Technology Division,Argonne National Laboratory,Argonne, IL 60439.Search for other works by this author on:
-
Amorphization of Precipitates in Zircaloy under Neutron and Charged-Particle IrradiationByAT Motta,AT Motta1Research Fellow, Research Engineer, and Head of Laboratory, respectively,CEA/DRN/SECC Centre d'Etudes Nucleaires de Grenoble/SECC, 85x,38041 GrenobleCEDEX,.FranceSearch for other works by this author on:F Lefebvre,F Lefebvre1Research Fellow, Research Engineer, and Head of Laboratory, respectively,CEA/DRN/SECC Centre d'Etudes Nucleaires de Grenoble/SECC, 85x,38041 GrenobleCEDEX,.FranceSearch for other works by this author on:C LemaignanC Lemaignan1Research Fellow, Research Engineer, and Head of Laboratory, respectively,CEA/DRN/SECC Centre d'Etudes Nucleaires de Grenoble/SECC, 85x,38041 GrenobleCEDEX,.FranceSearch for other works by this author on:
-
Oxide Characteristics and Their Relationship to Hydrogen Uptake in Zirconium AlloysByBD Warr,BD Warr1Ontario Hydro Research Division,Toronto, Ontario,.CanadaW8Z 5S4Search for other works by this author on:MB Elmoselhi,MB Elmoselhi1Ontario Hydro Research Division,Toronto, Ontario,.CanadaW8Z 5S4Search for other works by this author on:SB Newcomb,SB Newcomb2Cambridge University,.England, CB2 3QZSearch for other works by this author on:NS McIntyre,NS McIntyre3University of Western Ontario,London, Ontario,.CanadaN6A 5B7Search for other works by this author on:AM Brennenstuhl,AM Brennenstuhl1Ontario Hydro Research Division,Toronto, Ontario,.CanadaW8Z 5S4Search for other works by this author on:PC LichtenbergerPC Lichtenberger1Ontario Hydro Research Division,Toronto, Ontario,.CanadaW8Z 5S4Search for other works by this author on:
-
The Corrosion of Zircaloy-4 Fuel Cladding in Pressurized Water ReactorsByLFP Van Swam,LFP Van Swam1Advanced Nuclear Fuels Corporation,Richland, WA 99352.Search for other works by this author on:SH ShannSH Shann1Advanced Nuclear Fuels Corporation,Richland, WA 99352.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.
© 1991
ASTM International
