Redistribution of alloying elements in Zircaloy-2 after in-reactor exposure

被引：57
|
作者：
Sundell, G. [1 ]
Thuvander, M. [1 ]
Tejland, P. [2 ]
Dahlback, M. [3 ]
Hallstadius, L. [3 ]
Andren, H. -O. [1 ]
机构：
[1] Chalmers, Dept Appl Phys, SE-41296 Gothenburg, Sweden
[2] Studsvik Nucl AB, SE-61182 Nykoping, Sweden
[3] Westinghouse Elect Sweden, SE-721 Vasteras, Sweden
来源：
JOURNAL OF NUCLEAR MATERIALS | 2014年 / 454卷 / 1-3期
基金：
瑞典研究理事会;
关键词：
ATOM-PROBE TOMOGRAPHY; ZIRCONIUM ALLOYS; ZR ALLOYS; IRRADIATION; DIFFUSION; OXIDATION; EVOLUTION; METAL;
D O I：
10.1016/j.jnucmat.2014.07.072
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
An atom probe tomography study of the microstructure of a Zircaloy-2 material subjected to 9 annual cycles of BWR exposure has been conducted. Upon dissolution of secondary phase particles, Fe and Cr are seen to reprecipitate in large numbers of clusters and particles of 1-5 nm sizes throughout the Zr metal matrix. Fe and Sn were observed to segregate to ring-shaped features in the metal that are interpreted to be < c >-component vacancy loops. This implies that these two elements play a major role in the irradiation growth phenomenon in Zr alloys, which is believed to be caused by the formation of < c >-loops. Similarly to autoclave-corroded Zr alloys, the formation of a sub-oxide layer of approximate composition ZrO was observed. On the other hand, no oxygen saturated metal phase was detected underneath the oxide scale. (C) 2014 Elsevier B.V. All rights reserved.
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页码：178 / 185
页数：8
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