Congcong Zhao , Junhong Jia , Kui Wang , Xiaoyu Jiao , Runze Wei , Jian Wang , Jie Yang , Yaoqiang Tang , Qingqing Zhang , Zongyu Zhang
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引用次数: 0
Abstract
This study systematically investigates the critical influence of Fe³⁺ impurity ions on the corrosion behavior of boron carbide (B4C) -reinforced silicon carbide (SiC) composite ceramics in FLiNaK molten salt. SiC-B₄C composites were fabricated via hot-press sintering, and their corrosion characteristics were compared in both original and Fe³⁺-contaminated environments. The results indicate that in pure molten salt, the addition of B₄C promotes the formation of a dense, graphitized carbon layer on the surface, which significantly enhances corrosion resistance. In contrast, the strong oxidizing power of Fe³⁺ disrupts the formation and stability of this protective layer. This disruption results in a loose, porous surface structure, a substantial increase in corrosion layer thickness and the creation of pathways for the corrosive melt penetration. Thermodynamic analysis further confirms that FeF₃, as a potent oxidizing agent, preferentially reacts with B₄C. Moreover, Fe³⁺ is regenerated through a cyclic disproportionation reaction (3Fe²⁺→2Fe³⁺+Fe), which intensifies the corrosion process. This work provides critical theoretical support for material selection and service-life assessment of structural components in molten salt reactors under practical operating conditions.
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.