含钛熔盐中 Ni-Mo-Cr-Nb 合金的腐蚀和钛脆性行为

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

Journal of Nuclear Materials Pub Date : 2024-10-09 DOI:10.1016/j.jnucmat.2024.155450

Xian-Wei Zheng , Li Jiang , Kai Wang , Qing-Chun Zhu , Jian-Ping Liang , Chao-Wen Li , Zhi-Jun Li , Guang-Dong Che

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引用次数: 0

摘要

与标准 GH3535 合金相比，研究了 Ni-Mo-Cr-Nb 基合金在含 Te 熔盐中的腐蚀和 Te 脆化行为。由于氟化物的负吉布斯形成能较低，且晶格扩散速度较慢，因此铌比铬更耐熔盐溶解。此外，还验证了 Ni-Mo-Cr-Nb 合金的抗脆性明显优于 GH3535 合金。我们的研究结果证实，Ni-Mo-Cr-Nb 合金是熔盐反应堆中最有前途的候选材料之一。

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Corrosion and Te embrittlement behaviors of Ni-Mo-Cr-Nb alloy in Te-containing molten salts

The corrosion and Te embrittlement behaviors of Ni-Mo-Cr-Nb based alloy in the Te-containing molten salts have been investigated as compared with the standard GH3535 alloy. Nb is more resistant to molten salt dissolution than Cr due to the less negative Gibbs formation energy of fluoride and the more sluggish lattice diffusion. Furthermore, it was verified the Ni-Mo-Cr-Nb alloy possesses the obvious better Te embrittlement resistance than GH3535 alloy. Our results confirmed that Ni-Mo-Cr-Nb alloy is one of the most promising candidate materials in molten salt reactors.

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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.