Behavior of U3Si2 Fuel and FeCrAl Cladding under Normal Operating and Accident Reactor Conditions
Author:
Affiliation:
1. Idaho National Lab. (INL), Idaho Falls, ID (United States)
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Office of Scientific and Technical Information (OSTI)
Cited by 5 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. Steady State and Transient Studies on Accident Tolerant Fuels for Pressurized Water Reactor;SSRN Electronic Journal;2022
2. Influence of Accident-Tolerant Fuel With Steel Cladding for Sustainable Heat Transfer in the Reactor Core of VVER-1200;ASME Open Journal of Engineering;2022-01-01
3. APPLICATION OF STUDSVIK’S CMS5 CODE SYSTEM TO ACCIDENT TOLERANT FUEL CORE DESIGN AND ANALYSIS;EPJ Web of Conferences;2021
4. Fuel performance optimization of U3Si2-SiC design during normal, power ramp and RIA conditions;Nuclear Engineering and Design;2019-11
5. Multiscale modeling of fission gas behavior in U3Si2 under LWR conditions;Journal of Nuclear Materials;2019-08
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