A Multicomponent Model of Radiation-induced Segregation for Commercial Stainless Steels

被引：15

作者：

Fukuya, Koji ^{[1
]}

Fujii, Katsuhiko ^{[1
]}

机构：

[1] Inst Nucl Safety Syst, Mihama, Fukui 9191205, Japan

来源：

JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY | 2009年 / 46卷 / 07期

关键词：

radiation-induced segregation; grain boundary; stainless steels; neutron irradiation; light water reactors; rate theory; vacancy; interstitial; GRAIN-BOUNDARY SEGREGATION; SOLUTE SEGREGATION; MICROSTRUCTURAL EVOLUTION; IRRADIATION; PHOSPHORUS; DEPENDENCE; SILICON; ALLOYS; BINARY;

D O I：

10.3327/jnst.46.744

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

A radiation-induced segregation model of the Fe-Cr-Ni-Si-Mo system was developed to predict the change in grain boundary composition in commercial stainless steels under neutron irradiation. Parametric survey showed that there were strong influences on segregation behavior for the binding of Si to an interstitial and the jump frequency of Ni and Si via interstitial mechanisms. Careful setting of these parameters using effective point defect migration energies resulted in a good agreement between calculated results and measured data for SUS316 stainless steels irradiated to 74 dpa in light water reactor. Model calculation qualitatively reproduced the effects of dose rate, temperature, and bulk composition reported in the literature.

引用

页码：744 / 752

页数：9

共 46 条

[1] The effect of dose rate on the response of austenitic stainless steels to neutron radiation [J].