In-PWR Irradiation Performance of Dilute Tin-Zirconium Advanced Alloys
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ASTM International
Cited by 13 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. Effect of Tin and Niobium on Corrosion and Hydrogen Pickup of Quaternary Zirconium Alloys in Ultra-Long-Term Autoclave Exposures;Zirconium in the Nuclear Industry: 20th International Symposium;2023-11-01
2. Advanced PWR Cladding Development through Extensive In-Reactor Testing;Zirconium in the Nuclear Industry: 20th International Symposium;2023-11-01
3. Current Perspectives on Zirconium Use in Light Water Reactor Fuel and Its Continued Use in Nuclear Power;Zirconium in the Nuclear Industry: 20th International Symposium;2023-11-01
4. Zircaloy-4 high temperature oxidation in atmospheres representative of SFP-LOCA: Investigation of the influence of a low temperature pre-oxidation scale;Journal of Nuclear Materials;2019-01
5. Current status of materials development of nuclear fuel cladding tubes for light water reactors;Nuclear Engineering and Design;2017-05
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