Miniature tensile test specimens for fusion reactor irradiation studies

R.L. Klueh
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引用次数: 39

Abstract

Three miniature sheet-type tensile specimens and a miniature rod-tensile specimen are being used in irradiation-damage studies for fusion reactor materials. Miniature specimens are also being used to determine design properties of irradiated materials. Consequently, a comparison of the tensile properties determined with these different specimens was made by testing cold-worked and solution-annealed Type 316 stainless steel sheet and rod at room temperature, 300°C and 600°C. Good agreement was observed when the properties obtained with the different specimens were compared, and all of the specimens can be used for irradiation-damage studies. However, there were small differences in the properties obtained using the different specimens, and it was recommended that before any miniature specimens are used to determine design-type properties, further studies be conducted.

聚变反应堆辐照研究用微型拉伸试样
三个微型薄片拉伸试样和一个微型棒拉伸试样被用于聚变反应堆材料的辐照损伤研究。微型试样也被用来确定辐照材料的设计特性。因此,通过在室温,300°C和600°C下测试冷加工和溶液退火的316型不锈钢板和棒,比较了这些不同试样所确定的拉伸性能。对不同试样的性能进行了比较,结果一致,所有试样均可用于辐照损伤研究。然而,使用不同的试样得到的性能差异不大,建议在使用任何微型试样来确定设计型性能之前,进行进一步的研究。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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