Reaction behavior of molten 316L stainless steel with B4C at 1450℃ during a core melt accident of BWR

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

Journal of Nuclear Materials Pub Date : 2025-02-18 DOI:10.1016/j.jnucmat.2025.155705

Tatsuya Kanno , Takayuki Iwama , Takumi Sato , Ayumi Itoh , Yuji Nagae , Ryo Inoue , Shigeru Ueda

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引用次数: 0

Abstract

In the severe accident at the Fukushima Daiichi Nuclear Power Station, molten core material migrated downward and generated fuel debris at the bottom of the containment vessel and other locations. The composition of the generated melt changes as it moves because it reacts with structural materials. The composition of fuel debris is determined by the initial melt composition and reactions during migration. In this study, the reaction rate between molten 316 L stainless steel and B₄C at 1450 °C was experimentally investigated, assuming that control rods would melt and stainless steel-based melts would stagnate in the lower plenum in boiling water reactors. The effect of H₂O gas on the reaction between the molten metal and B₄C was investigated, and an estimation of the rate-limiting process of the reaction and the rate of B₄C was carried out. The rate-limiting process of the reaction changed from the dissolution reaction of B₄C to the diffusion of alloying elements and the precipitation of carbon as the reaction proceeded. Including these rate-limiting processes, an overall dissolution rate of B₄C melting in the B₄C/molten stainless steel reaction at 1450 °C was obtained.

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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.