Effect of irradiation parameters on defect evolution in neutron irradiated tungsten

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY Journal of Nuclear Materials Pub Date : 2025-02-03 DOI:10.1016/j.jnucmat.2025.155673

M. Klimenkov , U. Jäntsch , M. Rieth , H.C. Schneider , D. Terentyev , W. Van Renterghem

{"title":"Effect of irradiation parameters on defect evolution in neutron irradiated tungsten","authors":"M. Klimenkov , U. Jäntsch , M. Rieth , H.C. Schneider , D. Terentyev , W. Van Renterghem","doi":"10.1016/j.jnucmat.2025.155673","DOIUrl":null,"url":null,"abstract":"<div><div>The article presents a microstructural examination of neutron-irradiated tungsten (W), that was irradiated to four damage doses of 0.1 dpa, 0.2 dpa, 0.5 dpa and 0.8 dpa and at four temperatures of 600°C, 800°C, 900°C and 1200°C in the BR2 material test reactor (Mol, Belgium). The irradiation parameters cover a wide range that enables a comprehensive study of defect formation and evolution. The experimental work includes imaging and quantitative analysis of radiation induced voids and dislocation loops as well as the visualization of the distribution of the transmutation induced Re and Os. It demonstrates the dose- and temperature-dependent evolution of defect's size and number density as well as the segregation behavior of Re and Os at these defects. It was proven that the size of the defects increases, while their number density decreases with increasing damage dose. The formation of nanometer-sized Re–Os precipitates with elongated shape was detected in samples irradiated at 0.8 dpa. The large-scale EDX analysis showed the influence of grain and sub-grain boundaries as well as line dislocations on defect formation and thus on Re and Os-segregation behavior.</div></div>","PeriodicalId":373,"journal":{"name":"Journal of Nuclear Materials","volume":"607 ","pages":"Article 155673"},"PeriodicalIF":2.8000,"publicationDate":"2025-02-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Journal of Nuclear Materials","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0022311525000686","RegionNum":2,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q3","JCRName":"MATERIALS SCIENCE, MULTIDISCIPLINARY","Score":null,"Total":0}

引用次数: 0

Abstract

The article presents a microstructural examination of neutron-irradiated tungsten (W), that was irradiated to four damage doses of 0.1 dpa, 0.2 dpa, 0.5 dpa and 0.8 dpa and at four temperatures of 600°C, 800°C, 900°C and 1200°C in the BR2 material test reactor (Mol, Belgium). The irradiation parameters cover a wide range that enables a comprehensive study of defect formation and evolution. The experimental work includes imaging and quantitative analysis of radiation induced voids and dislocation loops as well as the visualization of the distribution of the transmutation induced Re and Os. It demonstrates the dose- and temperature-dependent evolution of defect's size and number density as well as the segregation behavior of Re and Os at these defects. It was proven that the size of the defects increases, while their number density decreases with increasing damage dose. The formation of nanometer-sized Re–Os precipitates with elongated shape was detected in samples irradiated at 0.8 dpa. The large-scale EDX analysis showed the influence of grain and sub-grain boundaries as well as line dislocations on defect formation and thus on Re and Os-segregation behavior.

Abstract Image

查看原文

微信好友朋友圈 QQ好友复制链接

本刊更多论文

求助全文

约1分钟内获得全文去求助

来源期刊

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

期刊介绍： The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.