Evaluation of Hastelloy N alloys after nine years exposure to both a molten fluoride salt and air at temperatures from 700 to 560$sup 0$C
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Cited by 19 articles. 订阅此论文施引文献 订阅此论文施引文献,注册后可以免费订阅5篇论文的施引文献,订阅后可以查看论文全部施引文献
1. High‐Temperature Oxidation Behavior of Hastelloy N Alloy for Molten Salt Reactor at 650–980 °C;Advanced Engineering Materials;2024-07-18
2. Radionuclide tracing based in situ corrosion and mass transport monitoring of 316L stainless steel in a molten salt closed loop;Nature Communications;2024-04-10
3. Review on synergistic damage effect of irradiation and corrosion on reactor structural alloys;Nuclear Science and Techniques;2024-03
4. Evaluation and selection of eutectic salts combined with metal foams for applications in high-temperature latent heat thermal energy storage;Journal of Energy Storage;2024-01
5. In-Situ Analysis of Corrosion Products in Molten Salt: X-ray Absorption Reveals Both Ionic and Metallic Species;ACS Omega;2023-06-29
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