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Simulation study of stopping power and damage profiles of H/He plasma irradiation in tungsten and its alloys for fusion power plant
Journal of Radioanalytical and Nuclear Chemistry ( IF 1.6 ) Pub Date : 2022-08-05 , DOI: 10.1007/s10967-022-08415-w
Meriem El Marsi , Zakaria Elmaddahi , Imad Fechtal , Aouatif Dezairi

Tungsten (W) plays a crucial role in the lifetime of the plasma-facing components of DEMO. In order to avoid oxidation, W-based alloys have been studied as alternatives to W. In this work, the Monte Carlo SRIM-2013 simulation program was used to calculate the nuclear stopping power, electronic stopping power, amount of target vacancies, displacements, replacement collisions, and total target damage of W, W-Cr-Si, W-Cr-Ti, and W-Cr-Y by hydrogen and helium ion bombardment. It is found that W is resistant to vacancies, atomic displacement, and total damage compared to W-based alloys.



中文翻译:

H/He等离子体辐照在聚变电站钨及其合金中的停止本领和损伤曲线的模拟研究

钨 (W) 在 DEMO 面向等离子组件的使用寿命中起着至关重要的作用。为了避免氧化,已经研究了 W 基合金作为 W 的替代品。在这项工作中,使用 Monte Carlo SRIM-2013 模拟程序计算核停止能力、电子停止能力、目标空位量、位移、氢和氦离子轰击对 W、W-Cr-Si、W-Cr-Ti 和 W-Cr-Y 的置换碰撞和总目标损伤。发现与 W 基合金相比,W 对空位、原子位移和总损伤具有抵抗力。

更新日期:2022-08-06
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