金属<strong>W</strong>中辐照缺陷的产生、演化与热回复机制

doi:10.11900/0412.1961.2020.00228

金属学报

2021, Vol. 57

Issue (3): 257-271 DOI: 10.11900/0412.1961.2020.00228

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金属W中辐照缺陷的产生、演化与热回复机制

易晓鸥¹(

), 韩文妥¹, 刘平平¹, FERRONIFrancesco², 詹倩¹, 万发荣¹

^1.北京科技大学材料科学与工程学院北京 100083
^2.Department of Materials, University of Oxford, Oxford OX1 3PH, U. K.

Defect Production, Evolution, and Thermal Recovery Mechanisms in Radiation Damaged Tungsten

YI Xiaoou¹(

), HAN Wentuo¹, LIU Pingping¹, FERRONI Francesco², ZHAN Qian¹, WAN Farong¹

^1.School of Materials Science and Engineering, University of Science and Technology Beijing, Beijing 100083, China
^2.Department of Materials, University of Oxford, Oxford OX1 3PH, U. K.

引用本文:

易晓鸥, 韩文妥, 刘平平, FERRONIFrancesco, 詹倩, 万发荣. 金属W中辐照缺陷的产生、演化与热回复机制[J]. 金属学报, 2021, 57(3): 257-271.
Xiaoou YI, Wentuo HAN, Pingping LIU, Francesco FERRONI, Qian ZHAN, Farong WAN. Defect Production, Evolution, and Thermal Recovery Mechanisms in Radiation Damaged Tungsten[J]. Acta Metall Sin, 2021, 57(3): 257-271.

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摘要:

金属W是核聚变反应堆中面向等离子体部件的主要候选材料。服役期间，钨部件需要承受高温、高通量聚变反应中子轰击带来的辐照级联损伤。这些损伤主要表现为高浓度的点缺陷及团簇。它们与氢氦等离子体、嬗变反应的多种产物相互作用，导致辐照硬化、韧脆转变温度升高、导热能力下降等问题。本文围绕金属W的辐照级联损伤，基于显微缺陷实验表征与材料多尺度模拟计算，系统总结了辐照缺陷的产生、演化与热回复行为及作用机制。这些信息反映了材料中辐照缺陷特征的统计规律，构成定量描述微观损伤组织随时间尺度与空间尺度变化的依据，有利于钨部件性能的预测、服役可靠性评价以及未来新型材料部件的研发。

关键词 ：聚变堆, W, 辐照缺陷, 产生, 演化, 热回复

Abstract：

Tungsten (W) is a prime candidate for use in plasma-facing components in fusion reactors. These components are subjected to high temperatures and displacement damages caused by fusion neutron bombardments. The displacement damages are mainly present as high concentrations of point defects and clusters. They interact with the hydrogen, helium plasma, and various other transmutation products, giving rise to unwanted consequences, such as radiation hardening, increased brittle-to-ductile transition temperature, and thermal conductivity degradation. This review focuses on the radiation-induced displacement damage in tungsten and aims to provide a systematic summary of the underlying mechanisms for the production, evolution, and thermal recovery of radiation defect, using defect microscopy techniques and materials multiscale modeling. The information uncovered, reflects statistical laws of radiation defect characteristics; serves as the basis for a quantitative description of time- and space-dependent evolution of damage microstructure; and is in great favor of material property prediction, reliability evaluation, and the future development of novel materials.

Key words： fusion reactor W radiation defect production evolution thermal recovery

收稿日期: 2020-06-30

ZTFLH:

TG146.4

基金资助:国家自然科学基金项目(51701014)

作者简介: 易晓鸥，女，1984年生，副教授，博士

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https://www.ams.org.cn/CN/10.11900/0412.1961.2020.00228 或 https://www.ams.org.cn/CN/Y2021/V57/I3/257

图1 金属W单个碰撞级联内辐照缺陷的空间分布统计[55](a) high-precision automated defect cluster detection and size analysis based on the mapping of defect contrasts to 2D Gaussians(b) analysis of spatial correlations of radiation defects based on 2D pairwise radial distribution function. ρ represents the separation distance of radiation defects. Conditions adopted for experiment data collection: 50-400 keV W+ irradiation, 30 K, fluence about 1016 W+/m2 (no cascade overlap), weak-beam dark-field contrast imaging with g= 200 and 110, excitation error sg=0.12-0.17 nm-1

图2 辐照缺陷的演化行为[47](a) 1D long-range migration of self-interstitial clusters (pure W, 150 keV W+ irradiation, 573-1073 K)(b) elastic interactions and coalescence reactions between radiation defects favoured loop raft formation and loop growth (W-5%V, 150 keV W+ irradiation, 1073 K)

图3 辐照剂量率对纯W辐照缺陷(位错环或孔洞)数密度的影响(图中所有文献数据均对应辐照缺陷数量未达饱和的情况。为便于比较分析，纵坐标的辐照缺陷数密度表示为单位体积内每平均累积1 dpa损伤而产生的辐照位错环或孔洞数量)[14,76,85,86]

图4 金属W经2 MeV W+ 离子辐照(773 K，1.5 dpa)后的损伤组织热回复过程原位观察[119]

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