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Digital Library / STP / STP1295-EB
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Zirconium in the Nuclear Industry: Eleventh International Symposium
Bradley ER
Pages: 898
Published: 1996
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Table of Contents
Learning from History: A Case Study in Nuclear Fuel
Robertson JAL
Behavior and Properties of Zircaloys in Power Reactors: A Short Review of Pertinent Aspects in LWR Fuel
Garzarolli F, Stehle H, Steinberg E
Microstructure of Oxides on Zircaloy-4, 1.0Nb Zircaloy-4, and Zircaloy-2 Formed in 10.3-MPa Steam at 673 K
Anada H, Takeda K
The Importance of Oxide Morphology for the Oxidation Rate of Zirconium Alloys
Wikmark G, Rudling P, Lehtinen B, Hutchinson B, Oscarsson A, Ahlberg E
Effect of Annealing Temperature on Corrosion Behavior and ZrO Microstructure of Zircaloy-4 Cladding Tube
Anada H, Herb BJ, Nomoto K, Hagi S, Graham RA, Kuroda T
Microstructure of Oxide Films Formed during the Waterside Corrosion of the Zircaloy-4 Cladding in Lithiated Environment
Pêcheur D, Godlewski J, Billot P, Thomazet J
Mechanisms of LiOH Degradation and HBORepair of ZrO Films
Cox B, Ungurelu M, Wong Y-M, Wu C
PWR Zircaloy Fuel Cladding Corrosion Performance, Mechanisms, and Modeling
Cheng B, Gilmore PM, Klepfer HH
Correlation Between Electrochemical Properties and Corrosion Resistance of Zirconium Alloys
Ito Y, Furuya T
Long-Term In Situ Corrosion Investigation of Zr Alloys in Simulated PWR Environment by Electrochemical Measurements
Göhr H, Schaller J, Ruhmann H, Garzarolli F
Anodic Protection Provided by Precipitates in Aqueous Corrosion of Zircaloy
Isobe T, Murai T, Mae Y
Investigation of In-Pile Grown Corrosion Films on Zirconium-Based Alloys
Gebhardt O, Hermann A, Bart G, Blank H, Garzarolli F, Ray ILF
Microstructure Evolutions and Iron Redistribution in Zircaloy Oxide Layers: Comparative Effects of Neutron Irradiation Flux and Irradiation Damages
Iltis X, Lefebvre F, Lemaignan C
Oxide Characteristics and Corrosion and Hydrogen Uptake in Zr-2.5 Nb CANDU Pressure Tubes
Warr BD, Van Der Heide PAW, Maguire MA
The Effect of the Trace Impurity Uranium on PWR Aqueous Corrosion of Zircaloy-4
Peters HR, Harlow JL
Detrimental Role of Hydrogen on the Corrosion Rate of Zirconium Alloys
Blat M, Noel D
Hydrogen Pickup and Redistribution in Alpha-Annealed Zircaloy-4
Kammenzind BF, Franklin DG, Peters HR, Duffin WJ
A Unified Model to Describe the Anisotropic Viscoplastic Behavior of Zircaloy-4 Cladding Tubes
Delobelle P, Robinet P, Bouffioux P, Geyer P, Le Pichon I
The Influence of Temperature and Yield Strength on Delayed Hydride Cracking in Hydrided Zircaloy-2
Efsing P, Pettersson K
Effects of Hydride Precipitate Localization and Neutron Fluence on the Ductility of Irradiated Zircaloy-4
Garde AM, Smith GP, Pirek RC
Fracture Toughness of Zircaloy Cladding Tubes
Grigoriev V, Josefsson B, Rosborg B
A Model for Analysis of the Effect of Final Annealing on the In- and Out-of-Reactor Creep Behavior of Zircaloy Cladding
Limbäck M, Andersson T
Properties of an Irradiated Heat-Treated Zr-2.5Nb Pressure Tube Removed From the NPD Reactor
Chow CK, Coleman CE, Koike MH, Causey AR, Ells CE, Hosbons RR, Sagat S, Urbanic VF, Rodgers DK
Link Between Results of Small- and Large-Scale Toughness Tests on Irradiated Zr-2.5Nb Pressure Tube Material
Davies PH, Shewfelt RSW
Modeling In-Reactor Deformation of Zr-2.5Nb Pressure Tubes in CANDU Power Reactors
Christodoulou N, Causey AR, Holt RA, Tomé CN, Badie N, Klassen RJ, Sauvé R, Woo CH
Effect of In-PWR Irradiation on Size, Structure, and Composition of Intermetallic Precipitates of Zr Alloys
Garzarolli F, Goll W, Seibold A, Ray I
In Situ Studies of Phase Transformations in Zirconium Alloys and Compounds Under Irradiation
Motta AT, Faldowski JA, Howe LM, Okamoto PR
Evolution of Microstructure in Zirconium Alloys During Irradiation
Griffiths M, Mecke JF, Winegar JE
Influence of Neutron Irradiation on Dislocation Structure and Phase Composition of Zr-Base Alloys
Shishov VN, Nikulina AV, Markelov VA, Peregud MM, Kozlov AV, Averin SA, Kolbenkov SA, Novoselov AE
Non-Linear Irradiation Growth of Cold-Worked Zircaloy-2
Holt RA, Causey AR, Christodoulou N, Griffiths M, Ho ETC, Woo CH
Influence of Iron in the Nucleation of c Component Dislocation Loops in Irradiated Zircaloy-4
de Carlan Y, Regnard C, Griffiths M, Gilbon D, Lemaignan C
Effects of Extrusion-Billet Preheating on the Microstructure and Properties of Zr-2.5Nb Pressure Tube Materials
Choubey R, Aldridge SA, Theaker JR, Cann CD, Coleman CE
Zircaloy-2 Lined Zirconium Barrier Fuel Cladding
Williams CD, Marlowe MO, Adamson RB, Wisner SB, Rand RA, Armijo JS
Effects of Microstructure on Ductility and Fracture Resistance of Zr-1.2Sn-1 Nb-0.4Fe Alloy
Nikulin SA, Goncharov VI, Markelov VA, Shishov VN
Influence of Processing Variables and Alloy Chemistry on the Corrosion Behavior of ZIRLO Nuclear Fuel Cladding
Comstock RJ, Schoenberger G, Sabol GP
Effects of Thermomechanical Processing on In-Reactor Corrosion and Post-Irradiation Mechanical Properties of Zircaloy-2
Huang PY, Mahmood ST, Adamson RB
Embrittlement of Reactor Core Materials
Kreyns PH, Bourgeois WF, White CJ, Charpentier PL, Kammenzind BF, Franklin DG
Zirconium Alloy E635 as a Material for Fuel Rod Cladding and Other Components of VVER and RBMK Cores
Nikulina AV, Markelov VA, Peregud MM, Bibilashvili YK, Kotrekhov VA, Lositsky AF, Kuzmenko NV, Shevnin YP, Shamardin VK, Kobylyansky GP, Novoselov AE
Corrosion Behavior of Duplex and Reference Cladding in NPP Grohnde
Besch OA, Yagnik SK, Woods KN, Eucken CM, Bradley ER
Development of New Zirconium Alloys for a BWR
Etoh Y, Shimada S, Yasuda T, Ikeda T, Adamson RB, Chen J-SF, Ishii Y, Takei K
Comparison of the Long-Time Corrosion Behavior of Certain Zr Alloys in PWR, BWR, and Laboratory Tests
Garzarolli F, Broy Y, Busch RA
In-BWR and Out-of-Pile Nodular Corrosion behavior of Zry-2/4 Type Melts with Varying Fe, Cr, and Ni Content and Varying Process History
Ruhmann H, Manzel R, Sell H-J, Charquet D
Development of Pressure Tubes with Service Life Greater Than 30 Years
Coleman CE, Cheadle BA, Cann CD, Theaker JR
Author Index
Subject Index
Committee: B10
Paper ID: STP1295-EB
DOI: 10.1520/STP1295-EB
 ASTM International is a member of CrossRef.
0-8031-2406-6
978-0-8031-2406-6
STP1295-EB
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