A neutronic investigation of tristructural isotropic-duplex fuel in a high-temperature reactor prismatic seed-and-blanket fuel block configuration with reduced power peaking
Combustion; Fuels; High temperature engineering; Monte Carlo methods; Oxide minerals; Thoria; Uranium dioxide; High temperature engineering test reactors; Monte carlo n particles; Multiplication factor; Neutron flux distributions; Neutronic analysis; Power Optimization; Reactor modeling; Reference m...
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| 主要な著者: | , , |
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| フォーマット: | 論文 |
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John Wiley and Sons Ltd
2023
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| 要約: | Combustion; Fuels; High temperature engineering; Monte Carlo methods; Oxide minerals; Thoria; Uranium dioxide; High temperature engineering test reactors; Monte carlo n particles; Multiplication factor; Neutron flux distributions; Neutronic analysis; Power Optimization; Reactor modeling; Reference modeling; High temperature reactors |
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