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.

引用

页码：178 / 185

页数：8

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