Weldability of neutron irradiated austenitic stainless steels

Weldability of neutron irradiated austenitic stainless steels
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中子辐照奥氏体不锈钢的焊接性

DOI:
10.1016/s0022-3115(98)00491-7
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发表时间:
1999
影响因子:
3.1
通讯作者:
T. Hashimoto
T. Hashimoto
中科院分区:
工程技术2区
文献类型:
--
作者:
K. Asano;S. Nishimura;Saito Yoshiaki;H. Sakamoto;Yuji Yamada;Takahiko Kato;T. Hashimoto

文献摘要

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中子辐照奥氏体不锈钢的焊接性退化是规划轻水反应堆堆芯内部构件主动维护需要解决的一个重要问题。在本工作中,从反应堆内部部件中选择了辐照剂量从8.5×1022到1.4×1026n/m2(E>1 MeV)的样品,分别对应于氦含量从0.11到103appm的样品,进行了钨极惰性气体保护焊(TIG),热输入为0.6-16kJ/cm。通过渗漏试验和断面金相分析对焊缝缺陷进行表征。当氦含量较少、热输入较低时,焊缝的完整性较好。当氦含量为0.6appm时,焊缝的拉伸性能满足未辐照母材的要求。反复的热循环被发现是非常危险的。结果表明,材料的氦含量和焊接线能量的组合,在材料可以焊接的情况下,不会引起裂纹。此外,还认识到使用适当选择的焊接程序以最大限度地减少热循环的重要性。
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 8.5×1022to 1.4×1026n/m2(E>1 MeV) corresponding to helium content from 0.11 to 103 appm, respectively, were subjected to tungsten inert gas arc (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.