Deyang Cui

Possible scenarios for the transition to thorium fuel cycle in molten salt reactor by using enriched uranium

Deyang Cui, X.X. Li, Shaopeng Xia et al. · Progress in Nuclear Energy · 2017 · 48 citations

Engineering, Nuclear Engineering, Nuclear Fuel Cycle +16

Transition toward thorium fuel cycle in a molten salt reactor by using plutonium

Deyang Cui, Shaopeng Xia, X.X. Li et al. · Nuclear Science and Techniques · 2017 · 35 citations

Engineering, Geology, Nuclear Engineering +14

Development of a Molten Salt Reactor specific depletion code MODEC

Shaopeng Xia, Jingen Chen, Wei Guo et al. · Annals of Nuclear Energy · 2018 · 33 citations

Engineering, Nuclear Engineering, Computational Heat Transfer +9

Preconceptual nuclear design of a 50 kWth heat pipe cooled micro molten salt reactor (micro-MSR)

Deyang Cui, Ye Dai, X. Z. Cai et al. · Progress in Nuclear Energy · 2021 · 33 citations

Engineering, Mechanical Engineering, Nuclear Engineering +16

Analysis of Th-U breeding capability for an accelerator-driven subcritical molten salt reactor

Xue-Chao Zhao, Deyang Cui, X. Z. Cai et al. · Nuclear Science and Techniques · 2018 · 20 citations

Engineering, Nuclear Engineering, Heat Transfer +11