Effect of irradiation parameters on defect evolution in neutron irradiated tungsten

IF 3.2 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

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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.

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辐照参数对中子辐照钨缺陷演化的影响

本文介绍了在BR2材料试验堆（Mol, Belgium）中以0.1 dpa、0.2 dpa、0.5 dpa和0.8 dpa四种损伤剂量和600°C、800°C、900°C和1200°C四种温度辐照的中子辐照钨(W)的显微结构。辐照参数覆盖范围广，可以全面研究缺陷的形成和演变。实验工作包括辐射诱导空洞和位错环的成像和定量分析，以及嬗变诱导的Re和Os分布的可视化。研究了缺陷尺寸和数量密度随剂量和温度的变化，以及缺陷处Re和Os的偏析行为。结果表明，随着损伤剂量的增加，缺陷尺寸增大，缺陷数量密度减小。在0.8 dpa辐照下，样品中检测到纳米尺寸的Re-Os长条形沉淀的形成。大尺度EDX分析表明，晶界和亚晶界以及线位错对缺陷形成的影响，从而对Re和os偏析行为产生影响。

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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.