TRISO Fuel Performance: Modeling, Integration into Mainstream Design Studies, and Application to a Thorium-fueled Fusion-Fission Hybrid Blanket
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1. Univ. of California, Berkeley, CA (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. Estimation of Waste Package Inventories and Characteristics from Different Advanced Fuel Cycles;Nuclear Technology;2023-02-01
2. Modeling the performance of TRISO-based fully ceramic matrix (FCM) fuel in an LWR environment using BISON;Nuclear Engineering and Design;2018-08
3. Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview;Annals of Nuclear Energy;2017-09
4. Thorium Fuel Cycles with Externally Driven Systems;Nuclear Technology;2016-05
5. Assembly Design of Pressurized Water Reactors with Fully Ceramic Microencapsulated Fuel;Nuclear Technology;2016-04
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