Austenitic Stainless Steels for Fast Reactors - Irradiation Experiments, Property Evaluation and Microstructural Studies

被引：31

作者：

Karthik, V. ^{[1
]}

Murugan, S. ^{[1
]}

Parameswaran, P. ^{[1
]}

Venkiteswaran, C. N. ^{[1
]}

Gopal, K. A. ^{[1
]}

Muralidharan, N. G. ^{[1
]}

Saroja, S. ^{[1
]}

Kasiviswanathan, K. V. ^{[1
]}

机构：

[1] Indira Gandhi Ctr Atom Res, Met & Mat Grp, Kalpakkam 603102, Tamil Nadu, India

来源：

ASIAN NUCLEAR PROSPECTS 2010 | 2011年 / 7卷

关键词：

Fast reactors; stainless steel; mechanical properties; void swelling; neutron irradiation;

D O I：

10.1016/j.egypro.2011.06.033

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：

Austenitic stainless steel SS316 and its variants are the common materials for the fast reactor structural components. Using the Fast Breeder Test Reactor (FBTR) as an irradiation test bed, a systematic analysis of the irradiation performance of the austenitic stainless steel has been undertaken. The performance of 20 % cold worked SS316 has been assessed by examining the cladding and wrapper of FBTR at various displacement damages. The modified version of SS316, alloy D9, chosen for PFBR has been subjected to test irradiations in FBTR. Further modification of alloy D9 with respect to minor elements is also being studied The salient features of (i) mechanical and microstructural behaviour of SS316 at different fluence levels, (ii) the ongoing irradiation experiments on alloy D9 and (iii) microstructural studies on modified versions of alloy D9 are presented in this paper. (C) 2011 Published by Elsevier Ltd. Selection and/or peer-review under responsibility of Indra Gandhi Centre of Atomic Research

引用

页码：257 / 263

页数：7