中子辐照对国际热核实验堆用316L(N)钢力学性能的影响

S. Fabritsiev, A. Pokrovsky
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引用次数: 3

摘要

316L(N)钢用于国际热核实验反应堆部件的一个特点是,它将用于转化器和第一壁等部件,主要作为铜-不锈钢双金属成分的一部分。本研究的主要目的是评估热处理对316L(N)钢辐射硬化和脆化的影响。本文报道了低温中子辐照对316L(N)钢不同热处理后辐射硬化脆化影响的实验研究结果。将316L(N)钢试样在RBT-6和SM-2反应器中辐照,辐照温度分别为150°C和80°C,剂量范围为0.001 ~ 2 dpa。结果表明,热处理对316L(N)钢的辐射硬化和脆化没有显著影响。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Effect of neutron irradiation on the mechanical properties of 316L(N) steel for International Thermonuclear Experimental Reactor applications
One of the features peculiar to the application of 316L(N) steel for International Thermonuclear Experimental Reactor components is that it will be used in such components as the divertor and the first wall, mainly as part of the Cu–stainless steel bimetal composition. The main purpose of this investigation was to estimate the effect of heat treatment on the radiation hardening and embrittlement of 316L(N) steel. The report presents the results from an experimental investigation into the effect of low-temperature neutron irradiation on the radiation hardening and embrittlement in 316L(N) steel after different heat treatments. Specimens of 316L(N) steel were irradiated at T irr=150 and 80 °C in the dose range 0.001–2 dpa in the RBT-6 and SM-2 reactors. It is shown that heat treatment does not cause a significant effect on the radiation hardening and embrittlement of 316L(N) steel.
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Plasma Devices and Operations
Plasma Devices and Operations 物理-核科学技术
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