| 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 | 46 | 2018 |
| 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 | 34 | 2017 |
| 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 | 24 | 2021 |
| 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 | 7 | 2022 |
| 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 | 3 | 2017 |
| 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 | 1 | 2023 |
| 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 |
