{"title":"中子辐照iter级钨的显微结构分析及力学意义","authors":"Koray Iroc , Dmitry Terentyev , Wouter Van Renterghem , Dominique Schryvers","doi":"10.1016/j.fusengdes.2025.115466","DOIUrl":null,"url":null,"abstract":"<div><div>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.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115466"},"PeriodicalIF":2.0000,"publicationDate":"2025-09-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Microstructural analysis and mechanical implications of neutron-irradiated ITER-grade tungsten\",\"authors\":\"Koray Iroc , Dmitry Terentyev , Wouter Van Renterghem , Dominique Schryvers\",\"doi\":\"10.1016/j.fusengdes.2025.115466\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>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.</div></div>\",\"PeriodicalId\":55133,\"journal\":{\"name\":\"Fusion Engineering and Design\",\"volume\":\"222 \",\"pages\":\"Article 115466\"},\"PeriodicalIF\":2.0000,\"publicationDate\":\"2025-09-27\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Fusion Engineering and Design\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0920379625006623\",\"RegionNum\":3,\"RegionCategory\":\"工程技术\",\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q1\",\"JCRName\":\"NUCLEAR SCIENCE & TECHNOLOGY\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379625006623","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
Microstructural analysis and mechanical implications of neutron-irradiated ITER-grade tungsten
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.
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.