Review of conceptual design and fundamental research of molten salt reactors in ChinaDalin Zhang, G.H. Su, Limin Liu et al.|International Journal of Energy Research|2018Cited by 130
Experimental investigation of flow and convective heat transfer on a high-Prandtl-number fluid through the nuclear reactor pebble bed coreLimin Liu, G.H. Su, Dalin Zhang et al.|Applied Thermal Engineering|2018Cited by 57
Preliminary neutronic and thermal-hydraulic analysis of a 2 MW Thorium-based Molten Salt Reactor with Solid FuelLimin Liu, Suizheng Qiu, Dalin Zhang et al.|Progress in Nuclear Energy|2015Cited by 33
Experimental analysis of flow and convective heat transfer in the water-cooled packed pebble bed nuclear reactor coreLimin Liu, G.H. Su, Chenglong Wang et al.|Progress in Nuclear Energy|2020Cited by 30
Review of the experimental research on the thermal‐hydraulic characteristics in the pebble bed nuclear reactor core and fusion breeder blanketsLimin Liu, Hanyang Gu, Jian Deng et al.|International Journal of Energy Research|2020Cited by 25