Analysis of minor actinides transmutation for a Molten Salt Fast Reactor
Chenggang Yu, X.X. Li, X. Z. Cai, Chunyan Zou, Yuwen Ma, Jianlong Han, Jingen Chen
Abstract
Chenggang Yu, X.X. Li, X. Z. Cai, Chunyan Zou, Yuwen Ma, Jianlong Han, Jingen Chen
Abstract
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Key concepts: Nuclear transmutation, Fissile material, Nuclear engineering, Neutron transport, Spent nuclear fuel, Environmental science, Molten salt, Delayed neutron