Interaction between dislocations and cavities in tungsten during tensile test in a TEM at 723 K

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-02-14 DOI:10.1016/j.jnucmat.2025.155701

Kouichi Tougou , Maoto Fukui , Ken-ichi Fukumoto , Ryoya Ishigami

引用次数: 0

Abstract

The temperature dependencies of dislocation motion and the obstacle barrier strength α of cavities in tungsten were investigated at 723 K. Zig-zag motion and motion around pinning point of dislocations in pure tungsten were observed. The obstacle barrier strength α of a cavity with a 2 nm diameter in pure tungsten was measured to be 0.49±0.18. Approximately 41 % of the dislocations exhibited cross-slip and double cross-slip in the dynamic interaction between screw-type dislocations and cavities. The fraction of cross-slip and double cross-slip in screw-type dislocations increased with increasing test temperature.

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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.