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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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書誌詳細
主要な著者:	Rabir M.H., Ismail A.F., Yahya M.S.
その他の著者:	55898782000
フォーマット:	論文
出版事項:	John Wiley and Sons Ltd 2023
タグ:	タグ追加タグなし, このレコードへの初めてのタグを付けませんか!

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