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Cui D.Y
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Possible scenarios for the transition to thorium fuel cycle in molten salt reactor by using enriched uranium
Cui D.Y., Li X.X., Xia S.P., Zhao X.C., Yu C.G., Chen J.G., Cai X.Z.
Progress in Nuclear Energy 104, 75-84, 2018
462018
Transition toward thorium fuel cycle in a molten salt reactor by using plutonium
Cui D.Y., Xia S.P., Li X.X, Cai X. Z, Chen J. G.
Nuclear Science and Techniques 28 (10), 152, 2017
342017
Preconceptual nuclear design of a 50 kWth heat pipe cooled micro molten salt reactor (micro-MSR)
Cui D.Y., Dai Y., Cai X.Z., Fu Y., Li X.X., Zou Y., Chen J.G.
Progress in Nuclear Energy 134, 103670, 2021
242021
An improved core design of a 50 kWth heat pipe cooled micro Molten Salt Reactor (micro-MSR)
Cui D.Y., Li X.X., Dai Y., Hu G., Cai X.Z., Zou Y., Chen J.G.
Progress in Nuclear Energy 151, 104326, 2022
72022
Methodologies for single-fluid, two-zone MSR burnup calculation based on SCALE/TRITON
Cui D.Y., Xia S.P., Cai X.Z., Chen J.G., Yu C.G.
Nuclear Techniques 40 (8), 2017
32017
An assessment of scenarios for transuranic burning and 233U production in a small molten chloride fast reactor
Cui D.Y., Zhang A., Li X.X., Cai X.Z., Chen J.G., Zou Y.
Annals of Nuclear Energy 185, 109719, 2023
12023
Accident scenario analysis and control scheme design for a micro Molten Salt Reactor
Cui D.Y., Li X.X., Dai Y., Zou Y., Chen J.G., Cai X.Z.
Progress in Nuclear Energy 172 (105208), 2024
2024
Analysis of Sustainable Thorium Fuel Utilization in Molten Salt Reactors Starting From Enriched Uranium
Cui D.Y., Cai X.Z., Chen J.G., Yu C.G.
International Conference on Nuclear Engineering 57830, V005T05A033, 2017
2017
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