Burn-up calculation of the neutronic and safety parameters of thorium-uranium mixed oxide fuel cycle in a Westinghouse small modular reactor
收藏Mendeley Data2020-05-23 更新2026-04-09 收录
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https://data.mendeley.com/datasets/7ppwx856ms
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资源简介：
The datasets added here could be used to reproduce the burn-up calculation of the Neutronic and Safety parameters of thorium-uranium mixed oxide fuel using three fissile enrichment zones against the conventional single enrichment. The is meant to determine the choice of the three fissile enrichment for thorium-based fuel and its performance at long-lasting temperature differentials.
创建时间：
2020-05-23
