|
|
Digital Library /STP / STP1423-EB
|
|
Overview PDF
Description
Table of Contents
Simulating the Behavior of Zirconium-Alloy Components in Nuclear Reactors
Coleman CE
Physical Phenomena Concerning Corrosion Under Irradiation of Zr Alloys
Lemaignan C
Role of the Second-Phase Particles in Zirconium Binary Alloys
Barberis P, Ahlberg E, Simic N, Charquet D, Lemaignan C, Wikmark G, Dahlbäck M, Limbäck M, Tägtström P, Lehtinen B
Synchrotron Radiation Study of Second-Phase Particles and Alloying Elements in Zirconium Alloys
Motta AT, Erwin KT, Delaire O, Birtcher RC, Chu Y, Maser J, Mancini DC, Lai B
The Behavior of Intermetallic Precipitates in Highly Irradiated BWR LTP Cladding
Goll W, Ray L
Effects of Hydrogen Pickup and Second-Phase Particle Dissolution on the In-Reactor Corrosion Performance of BWR Claddings
Tägtstrom P, Limbäck M, Dahlbäck M, Andersson T, Pettersson H
Alternative Zr Alloys with Irradiation Resistant Precipitates for High Burnup BWR Application
Garzarolli F, Ruhmann H, Van Swam L
Mössbauer Investigations of the Chemical States of Tin and Iron Atoms in Zirconium Alloy Oxide Film
Pêcheur D, Filippov VP, Bateev AB, Ivanov JJ
Chemical State Analysis of Sn and Fe in ZrO by Mössbauer Spectroscopy
Anada H, Takeda K, Nasu S, Kobayashi Y, Nakamichi T
The Role of Lithium and Boron on the Corrosion of Zircaloy-4 Under Demanding PWR-Type Conditions
Billot P, Yagnik S, Ramasubramanian N, Peybernes J, Pêcheur D
Study of the Mechanisms Controlling the Oxide Growth Under Irradiation: Characterization of Irradiated Zircaloy-4 and Zr-1Nb-O Oxide Scales
Bossis P, Thomazet J, Lefebvre F
Hydrogen Evolution and Pickup During the Corrosion of Zirconium Alloys: A Critical Evaluation of the Solid State and Porous Oxide Electrochemistry
Ramasubramanian N, Billot P, Yagnik S
The Influence of Material Variables on Corrosion and Deuterium Uptake of Zr-2.5Nb Alloy During Irradiation
McDougall GM, Urbanic VF
The Cause for Enhanced Corrosion of Zirconium Alloys by Hydrides
Kim YS, Woo HK, Im KS, Kwun SI
The Effect of Minor Alloying Elements on Oxidation and Hydrogen Pickup in Zr-2.5Nb
Ploc RA
Role of Microchemistry and Microstructure on Variability in Corrosion and Deuterium Uptake of Zr-2.5Nb Pressure Tube Material
Warr BD, Perovic V, Lin YP, Wallace AC
Temperature and Hydrogen Concentration Limits for Delayed Hydride Cracking in Irradiated Zircaloy
Schofield JS, Darby EC, Gee CF
Experimental Study and Preliminary Thermodynamic Calculations of the Pseudo-Ternary Zr-Nb-Fe-(O,Sn) System
Toffolon C, Brachet J-C, Servant C, Legras L, Charquet D, Barberis P, Mardon JP
Activated Slip Systems and Localized Straining of Irradiated Zr Alloys in Circumferential Loadings
Regnard C, Verhaeghe B, Lefebvre-Joud F, Lemaignan C
Effects of Neutron Irradiation on the Microstructure of Alpha-Annealed Zircaloy-4
Bajaj R, Kammenzind BF, Farkas DM
Plastic Deformation and Fracture During the Zr1%Nb Tube Production
Zavodtchikov SY, Zuev LB, Belov VI, Lositskiy AF, Shevnin YP
Development of Crystallographic Texture in CANDU Calandria Tubes
Theaker JR, Coleman CE
Impact of Hydrogen on Dimensional Stability of ZIRLO Fuel Assemblies
King SJ, Kesterson RL, Yueh KH, Comstock RJ, Herwig WM, Ferguson SD
In-PWR Irradiation Performance of Dilute Tin-Zirconium Advanced Alloys
Garde AM, Smith GP, Pirek RC
Predicting the In-Reactor Mechanical Behavior of Zr-2.5Nb Pressure Tubes from Postirradiation Microstructural Examination Data
Griffiths M, Davies PH, Davies WG, Sagat S
The Influence of In-Situ Clad Straining on the Corrosion of Zircaloy in a PWR Water Environment
Kammenzind BF, Eklund KL, Bajaj R
Characteristics of Hydride Precipitation and Reorientation in Spent-Fuel Cladding
Chung HM, Daum RS, Hiller JM, Billone MC
Test Reactor Studies of the Shadow Corrosion Phenomenon
Andersson B, Limbäck M, Wikmark G, Hauso E, Johnsen T, Ballinger RG, Nystrand AC
An In-Reactor Simulation Test to Evaluate Root Cause of Secondary Degradation of Defective BWR Fuel Rod
Cheng B, Oberländer BC, Wiesenack W, Yagnik S, Turnbull J
The Effect of Short-Term Dry-Out Transients on the Cladding Properties of Fresh and Pre-Irradiated Fuel Rods
McGrath MA, Oberländer BC, Thorshaug S, Ruhmann H, Anegawa T, Hara T
Effects of Alpha-Beta Transformation on High Temperature (LOCA) Creep behavior of Zr-Alloys
Sell HJ, Ortlieb E
Influence of Hydrogen Content on the / Phase Transformation Temperatures and on the Thermal-Mechanical Behavior of Zy-4, M4 (ZrSnFeV), and M5 (ZrNbO) Alloys During the First Phase of LOCA Transient
Brachet J-C, Portier L, Forgeron T, Hivroz J, Hamon D, Guilbert T, Bredel T, Yvon P, Mardon J-P, Jacques P
On the Embrittlement of Zircaloy-4 Under RIA-Relevant Conditions
Daum RS, Majumdar S, Bates DW, Motta AT, Koss DA, Billone MC
Impact of Irradiation Defects Annealing on Long-Term Thermal Creep of Irradiated ircaloy-4 Cladding Tube
Cappelaere C, Limon R, Gilbon D, Bredel T, Rabouille O, Bouffioux P, Mardon JP
Influence of Composition and Condition on In-PWR Behavior of Zr-Sn-Nb-FeCrV Alloys
Seibold A, Garzarolli F
Influence of Zirconium Alloy Chemical Composition on Microstructure Formation and Irradiation Induced Growth
Shishov VN, Peregud MM, Nikulina AV, Shebaldov PV, Tselischev AV, Novoselov AE, Kobylyansky GP, Ostrovsky ZE, Shamardin VK
Quantitative Assessment of Irradiation Effect on Creep and Corrosion Properties of Zr-Base Alloys
Kido T, Senda Y, Tukuta Y, Hayashi H, Murai K
Variability of In-Reactor Diametral Deformation for Zr-2.5Nb Pressure Tubing
Griffiths M, Davies WG, Causey AR, Moan GD, Holt RA, Aldridge SA
About the Mechanisms Governing the Hydrogen Effect on Viscoplasticity of Unirradiated Fully Annealed Zircaloy-4 Sheet
Rupa N, Clavel M, Bouffioux P, Domain C, Legris A
Irradiation Creep Behavior of Zr-Base Alloys
Soniak A, L'Hullier N, Mardon J-P, Rebeyrolle V, Bouffioux P, Bernaudat C
The Effect of Small Concentrations of Sulfur on the Plasticity of Zirconium Alloys at Intermediate Temperatures
Ferrer F, Barbu A, Bretheau T, Crépin J, Willaime F, Charquet D
Author Index
Subject Index
Committee: B10
Paper ID: STP1423-EB
DOI: 10.1520/STP1423-EB
 ASTM International is a member of CrossRef.
0-8031-2895-9
978-0-8031-2895-8
STP1423-EB
|
|
 |
|
|
|
Copyright © 1996-2008 ASTM. All Rights Reserved.
ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA, 19428-2959 USA
|
|
