Effect of ion irradiation of the metal matrix on the oxidation rate of Zircaloy-4

被引：13
作者：
Tupin, Marc [1 ]
Verlet, Romain [1 ,4 ]
Colas, Kimberly [1 ]
Jublot, Michael [1 ]
Baldacchino, Gerard [2 ]
Wolski, Krzysztof [3 ]
机构：
[1] Univ Paris Sacaly, CEA Saclay, CEA DEN Serv Etud Mat Irradies, F-91191 Gif Sur Yvette, France
[2] Univ Paris Sacaly, CNRS, CEA, LIDYL, F-91191 Gif Sur Yvette, France
[3] Ecole Mines St Etienne, Ctr SMS, UMR5307, 158 Cours Fauriel, F-42023 St Etienne, France
[4] EDF, Ctr Renardieres, EDF R&D, F-77818 Ecuelles, Moret Sur Loing, France
来源：
CORROSION SCIENCE | 2018年 / 136卷
关键词：
Zircaloy-4; Oxidation; Irradiation; SIMS; Reactor conditions; TEMPERATURE PRESSURIZED-WATER; ZIRCONIUM ALLOYS; CORROSION KINETICS; IN-SITU; DAMAGE; MICROSTRUCTURE; ACCUMULATION; EVOLUTION; BEHAVIOR; REACTOR;
D O I：
10.1016/j.corsci.2018.02.023
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The oxidation kinetics acceleration observed in Zircaloy-4 cladding in Pressurized Water Reactor could be partially due to metal irradiation damage occuring in-pile. To check this assumption, several ion irradiation tests of the Zircaloy-4 metal matrix were performed to reproduce the evolution of the metallurgical state in reactor. This study showed that the amorphization process of the intermetallic precipitates (SPPs) does not change significantly the oxidation rate of Zircaloy-4. Implantation of iron in the matrix to simulate iron dissolution from the SPPs has no real impact on the corrosion kinetics. However proton irradiations at 350 degrees C producing < a > dislocation loops resulted in a significant increase in the oxidation rate.
引用
收藏
页码：28 / 37
页数：10
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