Influence of hydrogen on the oxygen solubility in Zircaloy-4

被引:12
作者
Guilbert-Banti, Severine [1 ]
Lacote, Pauline [1 ]
Taraud, Gaelle [1 ]
Berger, Pascal [2 ]
Desquines, Jean [1 ]
Duriez, Christian [1 ]
机构
[1] Inst Radioprotect & Surete Nucl, SEREX LE2M, Batiment 327,BP3, F-13115 St Paul Les Durance, France
[2] Univ Paris Saclay, CNRS, CEA, NIMBE, F-91191 Gif Sur Yvette, France
关键词
Oxygen; Hydrogen; Zircaloy-4; Phase diagram; PHASE-TRANSFORMATION; OXIDATION; ALLOYS;
D O I
10.1016/j.jnucmat.2015.11.019
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Despite the influence of hydrogen on the behavior of zirconium fuel cladding in many nuclear safety issues, the pseudo-binary Zircaloy-4 oxygen phase diagram still lacks of data, especially above 1000 degrees C. The aim of this study was to provide experimental data to better assess the influence of hydrogen on the oxygen solubility in Zircaloy-4. Homogenized two-phase Zircaloy-4 samples were elaborated from 300 to 1000 wppm pre-hydrided samples. Local distributions were characterized thoroughly using Electron Probe Micro-Analysis (EPMA) for oxygen and Elastic Recoil Detection Analysis (ERDA) for hydrogen. The data obtained in this work were included in the pseudo-binary Zircaloy-4 - oxygen phase diagram and have shown that hydrogen has limited influence on the alpha + beta -> beta transus. Regarding the alpha -> alpha + beta transus, no influence of hydrogen concentration in the alpha phase below 400 wppm was evidenced. (C) 2015 Elsevier B.V. All rights reserved.
引用
收藏
页码:228 / 236
页数:9
相关论文
共 17 条
[1]  
Beck RL, 1962, ASM T, V55, P542
[2]   Comments to papers of JH Kim et al. [1] and M. Grosse et al. [2] recently published in JNM "On the hydrogen uptake of Zircaloy-4 and M5™ alloys subjected to steam oxidation in the 1100-1250 °C temperature range" [J].
Brachet, J. -C. ;
Vandenberghe, V. .
JOURNAL OF NUCLEAR MATERIALS, 2009, 395 (1-3) :169-172
[3]  
Brachet J.C., 2001, ASTM STP
[4]  
Brachet J.C., 2008, ASTM STP
[5]   PSEUDOBINARY ZIRCALOY-OXYGEN PHASE-DIAGRAM [J].
CHUNG, HM ;
KASSNER, TF .
JOURNAL OF NUCLEAR MATERIALS, 1979, 84 (1-2) :327-339
[6]   THE INFLUENCE OF ALLOYING ELEMENTS ON THE TERMINAL SOLUBILITY OF HYDROGEN IN ALPHA-ZIRCONIUM [J].
ERICKSON, WH ;
HARDIE, D .
JOURNAL OF NUCLEAR MATERIALS, 1964, 13 (02) :254-262
[7]   Experiment and modeling of advanced fuel rod cladding behavior under LOCA conditions: Alpha-beta phase transformation kinetics and EDGAR methodology [J].
Forgeron, T ;
Brachet, JC ;
Barcelo, F ;
Castaing, A ;
Hivroz, J ;
Mardon, JP ;
Bernaudat, C .
ZIRCONIUM IN THE NUCLEAR INDUSTRY: TWELFTH INTERNATIONAL SYMPOSIUM, 2000, 1354 :256-278
[8]  
Le Saux M., 2011, WRFPM 2011
[9]   On the zirconium-oxygen-hydrogen ternary system [J].
Miyake, M ;
Uno, M ;
Yamanaka, S .
JOURNAL OF NUCLEAR MATERIALS, 1999, 270 (1-2) :233-241
[10]   THE HIGH-TEMPERATURE SOLUBILITY OF HYDROGEN IN PURE AND OXYGEN-CONTAINING ZIRCALOY [J].
MOALEM, M ;
OLANDER, DR .
JOURNAL OF NUCLEAR MATERIALS, 1991, 178 (01) :61-72