Zirconium in the Nuclear Industry: Thirteenth International Symposium

Format:

Book

Contributor:

Moan, Gerry D, Contributor.

Rudling, Peter, Contributor.

Series:

ASTM special technical publication ; 1423.

ASTM special technical publication ; 1423

Language:

English

Subjects (All):

Nuclear fuel claddings--Congresses.

Nuclear fuel claddings.

Zirconium alloys--Congresses.

Zirconium alloys.

Physical Description:

1 online resource (881 pages) : illustrations.

Other Title:

Zirconium in the Nuclear Industry

Place of Publication:

[Place of publication not identified] American Society for Testing & Materials 2002

Language Note:

English

Summary:

The 41 papers of this proceedings volume were first presented at the 13th symposium on Zirconium in the Nuclear Industry held in Annecy, France in June of 2001. Many of the papers are devoted to material related issues, corrosion and hydriding behavior, in-reactor studies, and the behavior and properties of Zr alloys used in storing spent fuel. Some papers report on studies of second phase particles, irradiation creep and growth, and material performance during loss of coolant and reactivity initiated accidents. Annotation copyrighted by Book News, Inc., Portland, OR.

Contents:

Simulating the Behavior of Zirconium-Alloy Components in Nuclear Reactors / CE Coleman

Physical Phenomena Concerning Corrosion Under Irradiation of Zr Alloys / C Lemaignan

Role of the Second-Phase Particles in Zirconium Binary Alloys

P Barberis, E Ahlberg, N Simic, D Charquet, C Lemaignan, G Wikmark, M Dahlbäck, M Limbäck, P / Tägtström, B Lehtinen

Synchrotron Radiation Study of Second-Phase Particles and Alloying Elements in Zirconium Alloys / AT Motta, KT Erwin, O Delaire, RC Birtcher, Y Chu, J Maser, DC Mancini, B Lai

The Behavior of Intermetallic Precipitates in Highly Irradiated BWR LTP Cladding / W Goll, L Ray

Effects of Hydrogen Pickup and Second-Phase Particle Dissolution on the In-Reactor Corrosion Performance of BWR Claddings / P Tägtstrom, M Limbäck, M Dahlbäck, T Andersson, H Pettersson

Alternative Zr Alloys with Irradiation Resistant Precipitates for High Burnup BWR Application / F Garzarolli, H Ruhmann, L Van Swam

Mössbauer Investigations of the Chemical States of Tin and Iron Atoms in Zirconium Alloy Oxide Film / D Pêcheur, VP Filippov, AB Bateev, JJ Ivanov

Chemical State Analysis of Sn and Fe in ZrO by Mössbauer Spectroscopy / H Anada, K Takeda, S Nasu, Y Kobayashi, T Nakamichi

The Role of Lithium and Boron on the Corrosion of Zircaloy-4 Under Demanding PWR-Type Conditions / P Billot, S Yagnik, N Ramasubramanian, J Peybernes, D Pêcheur

Study of the Mechanisms Controlling the Oxide Growth Under Irradiation: Characterization of Irradiated Zircaloy-4 and Zr-1Nb-O Oxide Scales / P Bossis, J Thomazet, F Lefebvre

Hydrogen Evolution and Pickup During the Corrosion of Zirconium Alloys: A Critical Evaluation of the Solid State and Porous Oxide Electrochemistry / N Ramasubramanian, P Billot, S Yagnik

The Influence of Material Variables on Corrosion and Deuterium Uptake of Zr-2.5Nb Alloy During Irradiation / GM McDougall, VF Urbanic

The Cause for Enhanced Corrosion of Zirconium Alloys by Hydrides / YS Kim, HK Woo, KS Im, SI Kwun

The Effect of Minor Alloying Elements on Oxidation and Hydrogen Pickup in Zr-2.5Nb / RA Ploc

Role of Microchemistry and Microstructure on Variability in Corrosion and Deuterium Uptake of Zr-2.5Nb Pressure Tube Material / BD Warr, V Perovic, YP Lin, AC Wallace

Temperature and Hydrogen Concentration Limits for Delayed Hydride Cracking in Irradiated Zircaloy / JS Schofield, EC Darby, CF Gee

Experimental Study and Preliminary Thermodynamic Calculations of the Pseudo-Ternary Zr-Nb-Fe-(O,Sn) System / C Toffolon, J-C Brachet, C Servant, L Legras, D Charquet, P Barberis, JP Mardon

Activated Slip Systems and Localized Straining of Irradiated Zr Alloys in Circumferential Loadings / C Regnard, B Verhaeghe, F Lefebvre-Joud, C Lemaignan

Effects of Neutron Irradiation on the Microstructure of Alpha-Annealed Zircaloy-4 / R Bajaj, BF Kammenzind, DM Farkas

Plastic Deformation and Fracture During the Zr1%Nb Tube Production / SY Zavodtchikov, LB Zuev, VI Belov, AF Lositskiy, YP Shevnin

Development of Crystallographic Texture in CANDU Calandria Tubes / JR Theaker, CE Coleman

Impact of Hydrogen on Dimensional Stability of ZIRLO Fuel Assemblies / SJ King, RL Kesterson, KH Yueh, RJ Comstock, WM Herwig, SD Ferguson

In-PWR Irradiation Performance of Dilute Tin-Zirconium Advanced Alloys / AM Garde, GP Smith, RC Pirek

Predicting the In-Reactor Mechanical Behavior of Zr-2.5Nb Pressure Tubes from Postirradiation Microstructural Examination Data / M Griffiths, PH Davies, WG Davies, S Sagat

The Influence of In-Situ Clad Straining on the Corrosion of Zircaloy in a PWR Water Environment / BF Kammenzind, KL Eklund, R Bajaj

Characteristics of Hydride Precipitation and Reorientation in Spent-Fuel Cladding / HM Chung, RS Daum, JM Hiller, MC Billone

Test Reactor Studies of the Shadow Corrosion Phenomenon / B Andersson, M Limbäck, G Wikmark, E Hauso, T Johnsen, RG Ballinger, AC Nystrand

An In-Reactor Simulation Test to Evaluate Root Cause of Secondary Degradation of Defective BWR Fuel Rod / B Cheng, BC Oberländer, W Wiesenack, S Yagnik, J Turnbull

The Effect of Short-Term Dry-Out Transients on the Cladding Properties of Fresh and Pre-Irradiated Fuel Rods / MA McGrath, BC Oberländer, S Thorshaug, H Ruhmann, T Anegawa, T Hara

Effects of Alpha-Beta Transformation on High Temperature (LOCA) Creep behavior of Zr-Alloys / HJ Sell, E Ortlieb

Influence of Hydrogen Content on the a/ß 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 / J-C Brachet, L Portier, T Forgeron, J Hivroz, D Hamon, T Guilbert, T Bredel, P Yvon, J-P Mardon, P Jacques

On the Embrittlement of Zircaloy-4 Under RIA-Relevant Conditions / RS Daum, S Majumdar, DW Bates, AT Motta, DA Koss, MC Billone

Impact of Irradiation Defects Annealing on Long-Term Thermal Creep of Irradiated ircaloy-4 Cladding Tube / C Cappelaere, R Limon, D Gilbon, T Bredel, O Rabouille, P Bouffioux, JP Mardon

Influence of Composition and Condition on In-PWR Behavior of Zr-Sn-Nb-FeCrV Alloys / A Seibold, F Garzarolli

Influence of Zirconium Alloy Chemical Composition on Microstructure Formation and Irradiation Induced Growth / VN Shishov, MM Peregud, AV Nikulina, PV Shebaldov, AV Tselischev, AE Novoselov, GP Kobylyansky, ZE Ostrovsky, VK Shamardin

Quantitative Assessment of Irradiation Effect on Creep and Corrosion Properties of Zr-Base Alloys / T Kido, Y Senda, Y Tukuta, H Hayashi, K Murai

Variability of In-Reactor Diametral Deformation for Zr-2.5Nb Pressure Tubing / M Griffiths, WG Davies, AR Causey, GD Moan, RA Holt, SA Aldridge

About the Mechanisms Governing the Hydrogen Effect on Viscoplasticity of Unirradiated Fully Annealed Zircaloy-4 Sheet / N Rupa, M Clavel, P Bouffioux, C Domain, A Legris

Irradiation Creep Behavior of Zr-Base Alloys / A Soniak, N L'Hullier, J-P Mardon, V Rebeyrolle, P Bouffioux, C Bernaudat

The Effect of Small Concentrations of Sulfur on the Plasticity of Zirconium Alloys at Intermediate Temperatures / F Ferrer, A Barbu, T Bretheau, J Crépin, F Willaime, D Charquet

Author Index

Subject Index.

Notes:

Bibliographic Level Mode of Issuance: Monograph

ISBN:

0-8031-5468-2