第一壁核聚变中子辐射损伤的蒙特卡罗研究

[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering Pub Date : 1991-09-30 DOI:10.1109/FUSION.1991.218688

X. Gao, Y. Hou, Z. Pan, Q.Y. Shao, J.X. Chen, S.M. Wu

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引用次数: 0

摘要

提出了蒙特卡罗中子输运程序(NTGM)和中子辐射损伤程序(NRDGM)来研究第一壁的辐射损伤。将该程序应用于静态多组分非晶靶。在平均壁负荷为1 MW/m/sup / 2的情况下，利用设计的中子能谱计算了第一壁(316型不锈钢)的PKA(主碰撞原子)能谱(30 eV至1 MeV)、平均原子位移率(16.8 dpa/a)、平均氦和氢产率(204 appm/a和623 appm/a)。结果表明，EHR的辐射损伤比纯聚变反应堆更严重。

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Monte-Carlo studies of radiation damage by fusion neutron in the first wall

A Monte Carlo Neutron Transport Program, NTGM, and Neutron Radiation Damage Program, NRDGM, are presented for studying radiation damage of the first wall. The programs are applied to a static multicomponent amorphous target. With the average wall load of 1 MW/m/sup 2/ the PKA (primary knock on atom) energy spectra (30 eV to 1 MeV), average displacement per atom rate (16.8 dpa/a), average helium and hydrogen production rates (204 appm/a and 623 appm/a) have been calculated for the first wall (type 316 stainless steel) using designed neutron spectra at the EHR (Experimental Hybrid Reactor) first wall. It is shown that the EHR's radiation damage is more serious than that of a pure fusion reactor.<>

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[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering

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