Microstructural analysis and mechanical implications of neutron-irradiated ITER-grade tungsten

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Koray Iroc , Dmitry Terentyev , Wouter Van Renterghem , Dominique Schryvers
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Abstract

This study examines the microstructural and hardening response of two ITER-grade pure tungsten materials, which were exposed to neutron irradiation at 600 °C and 1000 °C up to a dose of ∼1 dpa. Two major types of defects, dislocation loops and nanovoids, are observed for both grades and analyzed with transmission electron microscopy. While the general morphology and subgrain structure remained stable under irradiation, the number density of defects decreased, and average defect size increased at the higher irradiation temperature. Nanovoids exhibited greater thermal stability than dislocation loops, which led to their predominance in the radiation-induced hardening, particularly at 1000 °C. Hardening contributions were assessed using the dispersed barrier model, which showed that voids contributed more significantly to hardening than loops at any irradiation temperature. Various superposition rules are applied for the total hardening effect and the best fit is provided by squared summation with the size-dependent coefficient of barrier strength. The findings highlight the importance of void control and defect sink engineering in optimizing tungsten for fusion applications. This research aims to provide insights for designing radiation-resistant tungsten microstructure for advanced fusion reactor applications by linking defect behavior with mechanical properties under neutron irradiation.
中子辐照iter级钨的显微结构分析及力学意义
本研究考察了两种iter级纯钨材料的微观结构和硬化响应,这些材料分别暴露在600°C和1000°C至1 dpa剂量的中子辐照下。两种主要类型的缺陷,位错环和纳米空洞,观察和分析了两个等级的透射电子显微镜。辐照温度越高,缺陷数量密度越小,平均缺陷尺寸越大,但总体形貌和亚晶结构保持稳定。纳米孔洞比位错环表现出更强的热稳定性,这导致它们在辐射诱导硬化中占主导地位,特别是在1000℃时。使用分散屏障模型评估了硬化贡献,结果表明,在任何辐照温度下,空洞对硬化的贡献都大于环。对总硬化效应采用了不同的叠加规则,最优拟合是与阻挡层强度尺寸相关系数的平方求和。这些发现强调了空隙控制和缺陷汇工程在优化钨的聚变应用中的重要性。本研究旨在通过将中子辐照下的缺陷行为与力学性能联系起来,为设计用于先进聚变反应堆的抗辐射钨微结构提供见解。
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来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
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