首页> 美国政府科技报告 >Slow strain rate tensile tests in high temperature water of spectrally tailored irradiated type 316 materials for fusion reactor applications.
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Slow strain rate tensile tests in high temperature water of spectrally tailored irradiated type 316 materials for fusion reactor applications.

机译:用于聚变反应堆应用的光谱定制的辐照型316材料的高温水中的慢应变速率拉伸试验。

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摘要

The susceptibility of neutron irradiated type 316 stainless to stress corrosion cracking in oxygenated pure water was investigated by Slow Strain Rate Technique (SSRT). The specimens had been irradiated to 8 dpa in the Oak Ridge Research Reactor (ORR) und ...

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