混合堆第一壁中子辐照损伤模拟

利用蒙特卡罗程序和辐照损伤程序,通过构建模型,对常用的第一壁材料W,Fe,Be的中子辐照造成的离位损伤、裂变气体产生量进行了模拟计算,结果表明,混合堆与纯聚变堆相比,可以明显降低对第一壁材料的损伤要求。在W,Fe,Be三种材料之中,对于纯聚变堆来说,Be的离位损伤最小;对于混合堆来说,W的离位损伤、裂变气体产生量最低。从中子辐照损伤的角度来说,Be更适宜作纯聚变堆的第一壁材料,而W则更适宜作混合堆的第一壁材料。

Neutron irradiation damage for first wall materials in hybrid reactor

Displacement damage and fission gases production due to neutron irradiation damage of the first wall materials W, Fe and Be are analyzed by MC program and irradiation damage program. The results show that hybrid reactor can significantly reduce the requirements on damage of the first wall materials comparing with the pure fusion reactor. Among the materials W, Fe and Be, displacement damage of Be is the minimum for pure fusion reactor and displacement damage and fission gases of W are the minimum for hybrid reactor. From the point of view of neutron irradiation damage, Be is the most suitable for the first wall material of pure fusion reactor, while, W is the most suitable for the first wall material of hybrid reactor among the materials W, Fe and Be.