原位TEM双离子束辐照钨的位错环演化研究  

In-situ TEM Study of Dislocation Loop Evolution in Tungsten under Dual-ion Beam Irradiation

作　　者：马鹏飞 刘艳 曹留烜 张亚培[1] 李修锐 田文喜[1] 秋穗正[1] 苏光辉[1] MA Pengfei;LIU Yan;CAO Liuxuan;ZHANG Yapei;LI Xiurui;TIAN Wenxi;QIU Suizheng;SU Guanghui(School of Nuclear Science and Technology,Xi’an Jiaotong University,Xi’an 710049,China;School of Energy,Xiamen University,Xiamen 361105,China)

机构地区：[1]西安交通大学核科学与技术学院,陕西西安710049 [2]厦门大学能源学院,福建厦门361105

出　　处：《原子能科学技术》2025年第4期874-883,共10页Atomic Energy Science and Technology

基　　金：国家自然科学基金(12375173)。

摘　　要：钨由于在高温下具有优良的抗辐照性能而被认为可应用于聚变堆中面向等离子体材料(PFM,plasma-facing material)。聚变堆中产生大量热负荷和中子以及氢氦气体原子使钨的应用面临苛刻的环境考验。为了进一步探究钨应用于PFM时辐照损伤剂量对其辐照性能的影响机制,本文采用Kr^(+)&He^(+)双离子束以不同的辐照损伤剂量对钨进行辐照。通过原位TEM观察辐照损伤剂量对<100>和1/2<111>位错环的演化现象影响,并对其演化进行量化分析。结果表明,辐照损伤剂量的增加导致1/2<111>位错环生成与长大以及<100>位错环消失。Kr^(+)&He^(+)双离子束辐照下,<100>位错环的增殖与湮灭对钨的机械性能产生重大影响。本文深化了对钨的辐照损伤研究,为钨在聚变堆中的应用提供基础。Fusion reactors are regarded as the ultimate source of energy for addressing future power problems.However,prior to the building of fusion power plants,a number of scientific obstacles including significant degradation of plasma-facing material(PFM).Due to its excellent irradiation resistance at high temperature,tungsten is considered a promising PFM for fusion reactor.The application of tungsten in fusion reactor faces stringent environmental challenges,primarily due to the substantial thermal loads,neutron flux,and gas atoms such as hydrogen and helium generated during fusion.Numerous studies have employed ion irradiation to simulate the service environment of PFM and to develop fusion reactor materials with strong irradiation resistance.High-energy ion irradiation induces lattice defects,including interstitial atoms and vacancies,which often aggregate into twodimensional dislocation loops with Burgers vectors of 1/2<111> or <100> in body-centered cubic(BCC) materials.In the study of dislocation loops,the irradiation damage dose and damage rate significantly influence the formation and evolution of dislocation loops.Gas ion irradiation of tungsten materials exacerbates dislocation loop reactions,with the ratio of 1/2<111> to <100> dislocation loops varying with the irradiation damage dose.Current research on the irradiation resistance of tungsten mainly focuses on irradiation temperature,dose,and ion species effects of single ion beam or in-situ sequential beam irradiation,while studies on the synergistic effects by irradiation damage dose of simultaneous dual-ion beam irradiations in tungsten via in-situ TEM remain insufficient.Therefore,the present experiment primarily investigated the effects of varying irradiation damage doses on tungsten under high temperature conditions(700℃) using dual-ion beam Kr+& He+irradiation.In-situ TEM was employed to observe the evolution of <100> and 1/2<111> dislocation loops under different irradiation damage doses,with a quantitative analysis of the dislocation loop evoluti

关 键 词：面向等离子体材料 钨 双离子束辐照 原位TEM 位错环 

分 类 号：TL341[核科学技术—核技术及应用]