项目名称: 合金化元素(Ti/Nb/Re)对W中He起泡行为的影响及机理研究
项目编号: No.51471015
项目类型: 面上项目
立项/批准年度: 2015
项目学科: 一般工业技术
项目作者: 朱开贵
作者单位: 北京航空航天大学
项目金额: 84万元
中文摘要: 托卡马克装置中面对等离子体材料(PFM)的选择是聚变堆能否实现长期受控安全运行的关键之一,钨(W)被认为是重要的候选材料。W的辐照损伤问题直接影响PFM 的服役性能以及等离子体的稳定控制,已经成为目前急需解决的关键问题,其中等离子体辐照造成的W中He泡问题是辐照损伤的重要方面。W的合金化是改善W材料性能的重要手段。本项目从合金化元素与W中间隙位He之间的结合能、合金化元素对He在W中扩散行为的影响、合金化元素与W中空位的相互作用以及合金化元素对钨晶格结构的影响等方面,选取具有代表性的Ti、Nb、Re作为合金化元素,利用低能大束流直线等离子体发生装置等实验手段,进行等离子体辐照实验,研究这些合金化元素对W中He的滞留起泡行为的影响规律及其机制,评估合金化作为提高钨抗辐照性能的潜力或可行性,寻找抑制W中He泡的有效途径,为聚变装置中PFM的设计、制备、应用提供实验基础和参考依据。
中文关键词: 面对等离子体材料;氦泡;钨合金化;辐照损伤;托卡马克
英文摘要: The choice of plasma faced material (PFM) in Tokamak is one of the key factors which determines the long steady state operation and the safety of a device. Tungsten is now regarded as the most promising PFM candidates for the future Tokamak. However, the damage induced by irradiations limits its application performance and affect the plasma confinement, which has been one of the most important issues to be addressed.Helium bubble formation in tungsten is an important part of the damage caused by plasma irradiation. Alloying is one of the effective ways to improve W properties. In this project, titanium, niobium and rhenium are selected as the alloying elements based on the considerations including their bingding energy to helium in tungsten, their effects on the migration of helium in tungsten, their interaction with vacancies in tungsten and their effects on the lattice structure of tungsten. Through plasma irradiation experiments by using linear plasma generator with low-energy and large-fluence and other equipments, the effects of alloying elements on helium bubble formation as well as their mechanism will be investigated. Based on the results, the potential to improvement the irradiation resistence of tungsten through alloying elements will be evaluated in order to find effective ways to suppress the helium bubble in tungsten.The research result will be provided as a reference for design, fabrication and application of PFM in fusion devices.
英文关键词: plasma facing materials;helium bubble;tungsten alloying;irradiation damage;Tokamak