近服役环境下包层铸件结构材料中离位损伤的模拟研究

Simulation Study on Displacement Damage of Structural Materials for Blankets Casting of Fusion Reactor in Nearservice Environment

包层是聚变反应堆中靠近等离子体的重要部件,包层结构材料受到高能粒子轰击,其组织和性能可能发生显著变化。为了更好地发挥包层的辐射屏蔽作用,模拟研究了包层铸件候选结构材料CLAM钢和钒合金中的离位损伤。通过SRIM软件模拟聚变堆中的氢(H)、氘(D)、氦(He)三种离子分别注入CLAM钢和钒合金来观察材料的抗辐照能力,纯铁、纯钒作为基体参考。结果表明:相同剂量下三种离子注入靶材,在钒合金中产生的离位损伤(dpa)最小,这说明相较于CLAM钢、纯铁、纯钒三种材料,钒合金具有较高的抗辐照能力。同时,两种基体的离位损伤模拟分析发现,钒基体的抗中子辐照能力优于铁基体。此外,研究还发现,当同种离子在相同剂量下分别注入这四种材料中,H离子注入靶材料产生的离位损伤最低,He离子最高。这说明He离子在材料中产生的缺陷较多。

The blanket is an important part near the plasma in a fusion reactor,Casting process is one of its preparation methods.And the microstructure and properties of the structural materials for blankets may change significantly when bombarded by high-energy particles.In order to exert the radiation shielding effect of the blanket better,In this paper,the out-of-situ damage in CLAM steel and vanadium alloy,which are candidate structural materials of cladding prepared by casting process,is simulated.The three ions of hydrogen(H),deuterium(D),and helium(He)in the fusion reactor were simulated by SRIM software to be injected into CLAM steel and vanadium alloy respectively to observe the radiation resistance of the materials,and pure iron and pure vanadium were used as the matrix references.The results show that three ion implanted targets at the same dose have the smallest displacement damage(dpa)in the vanadium alloy,which indicates that the vanadium alloy has higher radiation resistance compared with the other three materials.At the same time,the simulation analysis of the out-of-situ damage of the two substrates shows that the resistance to neutron irradiation of the vanadium substrate is better than that of the iron substrate.In addition,the study also found that when the same ions were implanted into the four materials under the same dose,the ex-situ damage caused by H ions implanted into the target material was the lowest,and He ions were the highest.This shows that He ions produce more defects in the material.