Weldability of neutron irradiated austenitic stainless steels

被引:39
|
作者
Asano, K [1 ]
Nishimura, S
Saito, Y
Sakamoto, H
Yamada, Y
Kato, T
Hashimoto, T
机构
[1] Tokyo Elect Power Co Ltd, Mat Engn Grp, Yokohama, Kanagawa 2308510, Japan
[2] Nippon Nucl Fuel Dev Co Ltd, Ibaraki, Osaka, Japan
[3] Toshiba Corp, Appl Met & Chem Dept, Yokohama, Kanagawa, Japan
[4] Toshiba Corp, Nucl Energy & Chem Dept, Yokohama, Kanagawa, Japan
[5] Hitachi Ltd, Hitachi Works, Hitachi, Ibaraki, Japan
[6] Hitachi Ltd, Hitachi Res Lab, Hitachi, Ibaraki, Japan
关键词
D O I
10.1016/S0022-3115(98)00491-7
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Degradation of weldability in neutron irradiated austenitic stainless steel is an important issue to be addressed in the planning of proactive maintenance of light water reactor core internals. In this work, samples selected from reactor internal components which had been irradiated to fluence from 8.5 x 10(22) to 1.4 x 10(26) n/m(2) (E > 1 MeV) corresponding to helium content from 0.11 to 103 appm, respectively, were subjected to tungsten inert gas are (TIG) welding with heat input ranged 0.6-16 kJ/cm. The weld defects were characterized by penetrant test and cross-sectional metallography. The integrity of the weld was better when there were less helium and at lower heat input. Tensile properties of weld joint containing 0.6 appm of helium fulfilled the requirement for unirradiated base metal. Repeated thermal cycles were found to be very hazardous, The results showed the combination of material helium content and weld heat input where materials can be welded with little concern to invite cracking. Also, the importance of using properly selected welding procedures to minimize thermal cycling was recognized. (C) 1999 Elsevier Science B.V. All rights reserved.
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页码:1 / 9
页数:9
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