Non-electric mass transfer between stainless steel 316H and glassy carbon in NaF-KF-UF4 salt

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

Journal of Nuclear Materials Pub Date : 2024-11-20 DOI:10.1016/j.jnucmat.2024.155534

Jaewoo Park, Jinsuo Zhang

引用次数: 0

Abstract

This study focuses on non-electric mass transfer between stainless steel 316H (SS316H) and carbon materials in molten NaF-KF-UF₄ salt. To simulate the molten-salt flow and accelerate the mass transfer, an SS316H specimen was rotated with a tangential speed of 2 m/s in the molten salt contained in a glassy carbon crucible at 1073 K for 120 h. The concentrations of Cr, Fe, Ni, and Mn in the salt were measured as a function of time during the test. The depletion of Cr was observed near the surface of the post-test SS316H specimen, and Fe-concentrated layers were formed on the specimen. (Cr, Fe)₇C₃ layers, Cr-metal particles, and dendritic structures concentrated with Fe and Cr were observed on the post-test crucible, indicating the non-electric mass transfer between SS316H and glassy carbon.

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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.