Corrosion and resistance to irradiation of dissimilar weld joints of low activation materials for fusion reactor

点击翻译按钮获取中文摘要

In the present study, weld joints between low activation materials and commercial nuclear reactor materials were fabricated. Their mechanical properties, microstructures, fundamental irradiation properties and corrosion properties were investigated. Since irradiation hardening at weld metal of low activation ferritic steel-316L stainless steel joints were similar to that for the base metal 316L stainless steels, it is indicated that irradiation hardening and hence irradiation embrittlement are not enhanced in the weld metal. Corrosion tests on weld joints for low activation vanadium alloy exhibited no embrittlement. It is revealed that operation temperature limit for vanadium-316L stainless steel joints is below 600oC due to formation of brittle intermetalics.