In this paper, preliminary neutron physical properties of ceramic fast reactor (CFR) are simulated and analyzed. The CFR core consists of ceramic materials, including nuclear fuels, coolants, structural materials, reflective and absorption materials. These ceramics improve inherent safety levels substantially, increase breeding performance, and enhance the power-generation efficiency. The CFR has the potential to operate and breed more than 30 years. The performance of the CFR was simulated focusing on neutron-related effects. The parameters discussed contain fast neutron energy spectrum, the ideal effective multiplication-factor, nuclides mass changes, breeding performance, operation mode, etc. Furthermore, the strengths of the proposed reactor system are discussed. In the future nuclear energy system, CFR may be one of the existing alternative novel reactor type.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5145-6
PROCEEDINGS PAPER
Preliminary Neutron Simulation of Ceramic Fast Reactor
Xuesong Yan,
Xuesong Yan
Northwest Normal University, Lanzhou, China
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Xunchao Zhang,
Xunchao Zhang
Chinese Academy of Sciences, Lanzhou, China
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Yaling Zhang,
Yaling Zhang
Chinese Academy of Sciences, Lanzhou, China
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Lei Yang,
Lei Yang
Chinese Academy of Sciences, Lanzhou, China
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Wenshan Duan
Wenshan Duan
Northwest Normal University, Lanzhou, China
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Xuesong Yan
Northwest Normal University, Lanzhou, China
Xunchao Zhang
Chinese Academy of Sciences, Lanzhou, China
Yaling Zhang
Chinese Academy of Sciences, Lanzhou, China
Lei Yang
Chinese Academy of Sciences, Lanzhou, China
Wenshan Duan
Northwest Normal University, Lanzhou, China
Paper No:
ICONE26-81474, V003T02A021; 6 pages
Published Online:
October 24, 2018
Citation
Yan, X, Zhang, X, Zhang, Y, Yang, L, & Duan, W. "Preliminary Neutron Simulation of Ceramic Fast Reactor." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory. London, England. July 22–26, 2018. V003T02A021. ASME. https://doi.org/10.1115/ICONE26-81474
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