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Preliminary Neutron Simulation of Ceramic Fast Reactor

[+] Author Affiliations
Xuesong Yan, Wenshan Duan

Northwest Normal University, Lanzhou, China

Xunchao Zhang, Yaling Zhang, Lei Yang

Chinese Academy of Sciences, Lanzhou, China

Paper No. ICONE26-81474, pp. V003T02A021; 6 pages
  • 2018 26th International Conference on Nuclear Engineering
  • Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory
  • London, England, July 22–26, 2018
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 978-0-7918-5145-6
  • Copyright © 2018 by ASME


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.

Copyright © 2018 by ASME



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