The Comparative Study of the Sodium Loss Reactivity Effect of Large Pu-U and Pu-Th Fast Reactors
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概要
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Fast reactors having a 3, 000 l core volume fueled with ceramic Pu-U and Pu-Th are compared with each other for their reactivity effects due to large-scale loss of coolant. Using one-dimensional multi-group calculation, the maximum volume fractions of fuel for both fast systems are determined on the assumption that total loss of sodium in the core should not result in positive reactivity effect. It is concluded that Pu-Th fast reactors can be charged with more than several volume percent of fuel above the limit applicable to Pu-U fast reactors.
- 一般社団法人 日本原子力学会の論文
著者
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Ohta Masao
Department Of Nuclear Engineering Kyoto University
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OHTA Masao
Department of Nuclear Engineering, Kyoto University, Kyoto-shi.
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