不锈钢氚渗透行为模拟研究进展  

Research Progress on Simulation of Tritium Permeation Behaviors in Stainless Steel

作　　者：魏世平 胡源[1] WEI Shi-ping;HU Yuan(State Key Laboratory of Fire Science,University of Science and Technology of China,Hefei 230026,China)

机构地区：[1]中国科学技术大学火灾科学国家重点实验室,安徽合肥230026

出　　处：《核化学与放射化学》2024年第6期519-529,I0001,共12页Journal of Nuclear and Radiochemistry

基　　金：安徽省自然科学基金资助项目(2308085QE134)。

摘　　要：氚作为聚变堆的燃料之一,在不锈钢结构材料中极易渗透,对本来稀缺的燃料造成极大的浪费,也给辐射防护带来巨大的成本。探究不锈钢的氚渗透行为对聚变堆氚自持和安全运行具有重要研究意义。本文介绍了不锈钢氚渗透机理以及国内外氚渗透行为模拟研究的主要方法和进展,分析了目前氚渗透行为模拟存在的问题,并展望了新的研究方向。指出直接用氚的实验研究较少,从而导致相应氚渗透数据不确定性较大。需深入研究聚变中子辐射效应下的不锈钢氚渗透行为,并进一步阐述辐照损伤、缺陷、位错、金属元素等因素的影响。经典氚渗透模型和单一的模拟方法并不能完全精确描述氚渗透行为,本文提出了一种现有氚渗透模拟方法的有机结合架构,可实现多尺度、多物理耦合精确模拟。Fusion energy is a kind of clean energy with very low pollution for large-scale production,and the current mainstream solution is magnetic confinement nuclear fusion,which is considered to be the most promising way to achieve commercial fusion power generation.Radioactive tritium,as one of the fuels of fusion reactors,is easily permeable in stainless steel structural material,which causes a huge waste of scarce fuel and also brings huge cost to radiation protection.It is important to study the tritium permeation behaviors in stainless steel for the tritium self-sufficiency and safe operation of fusion reactor.They are closely related to the structural safety of fusion reactor components,tritium extraction of blankets,fuel cycle of tritium plant as well as the protection of the public and environment.This paper introduces the mechanism of tritium permeation in stainless steel and main methods and research progress of tritium penetration behavior simulation both domestically and internationally,analyzes the existing problems in the simulation of tritium permeation behaviors,and looks forward to the new research direction.Hightemperature gas phase permeation(GDP),thermal desorption spectrum(TDS)and chemical etching methods are generally used to study the adsorption,dissociation,diffusion and desorption of hydrogen isotopes in direct use of tritium,which leads to the great uncertainty of the corresponding tritium permeation data,At present,the experimental research mainly focuses on the tritium permeability parameters of stainless steel and the degree of related influence factors,but no systematic theoretical system has been formed.The tritium permeation behaviors in stainless steel under the radiation of fusion neutron also need to be further studied,and explain the effects of radiation damage,surface stress,defects,dislocations,and impurity elements on tritium adsorption,tritium diffusion,tritium retention,and tritium desorption.The classical tritium permeation model and a single simulation method cannot accurately

关 键 词：聚变堆 不锈钢 氚渗透 理论模拟 

分 类 号：TL341[核科学技术—核技术及应用]