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EVALUATION OF LOW-TEMPERATURE SWELLING IN AUSTENITIC STAINLESS STEELS

机译:奥氏体不锈钢低温肿胀评价

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摘要

Major portions of structural materials of near-term fusion blankets and light water reactor core components are subject to neutron irradiation at low temperatures and low fluxes compared to those in typical void swelling studies using fast reactors. Observed swelling in austenitic stainless steels at temperatures below 673K are generally very small under typical fast reactor irradiation conditions, however, the amount of swelling might be significantly influenced by neutron flux, helium generation rate, etc. In this work, using a reaction rate theory model of swelling, the influences of such key irradiation parameters on low temperature swelling behavior in austenitic stainless steels will be demonstrated to aid the evaluation of swelling at low temperature and low neutron flux conditions.
机译:与使用快速反应器的典型空隙溶胀研究相比,近级融合毯和光水反应器芯部件的结构材料的主要部分受到低温下的中子辐射和低通量。在低于673k的温度下观察到奥氏体不锈钢中的肿胀通常在典型的快速反应器照射条件下非常小,但是,使用反应速度理论,在这项工作中可能会显着影响中子通量,氦生成率等。膨胀模型,将证明奥氏体不锈钢低温膨胀行为对低温膨胀行为的影响,以帮助评价低温和低中子通量条件下的溶胀。

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