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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不锈钢316H与玻璃碳在NaF-KF-UF4盐中的非电传质

本研究的重点是不锈钢316H （SS316H）与碳材料在熔融NaF-KF-UF4盐中的非电传质。为了模拟熔盐流动和加速传质，将SS316H试样在1073 K的玻碳坩埚中以2 m/s的切向速度旋转120 h。在测试过程中，测量了盐中Cr、Fe、Ni和Mn的浓度随时间的变化。试验后的SS316H试样表面出现Cr的损耗，并在试样表面形成了铁的富集层。在试后坩埚上观察到（Cr, Fe）7C3层、Cr-金属颗粒和集中Fe和Cr的枝晶结构，表明SS316H与玻碳之间发生了非电质传递。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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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.