•主要研究成果
L. M. Liu, D. L. Zhang, Q. Lv, K. P. Wang, S. Z. Qiu, Preliminary neutronic and thermal-hydraulic analysis of a 2 MW Thorium-based Molten Salt Reactor with Solid Fuel. Progress in Nuclear Energy, 86(2016), 1-10.
L. M. Liu, D. L. Zhang, Q. Q. Yan, R. X. Xu, C. L. Wang, et al., RELAP5 MOD3.2 modification and application to the transient analysis of a fluoride-salt-cooled high-temperature reactor. Annals of Nuclear Energy(Revising).
L. M. Liu, D. L. Zhang, M. Y. Zheng, S. Z. Qiu, et al., Calculation of core physics parameter of thorium molten salt reactor with solid fuel. Yuanzineng Kexue Jishu/Atomic Energy Science and Technology. 49(2015), 126-131.
L. M. Liu, Q. Q. Yan, D. L. Zhang, S. Z. Qiu, et al., Investigation of the modified Relap5 Mod 3.2 capability to simulate the transients of the fluoride-salt high-temperature reactors, Proceedings of the 24th International Conference on Nuclear Engineering(ICONE24), 2016, Charlotte,NC, USA.
D. L. Zhang, L. M. Liu, M. H. Liu, C. Gong, et al., Preliminary licensing analysis for a solid-fuel molten salt reactor, 11th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-11), October 9-13, 2016 , Gyeongju, Korea,.
S. Z. Qiu, D. L. Zhang, L. M. Liu, M. H. Liu, et al., Coupled neutronics/thermal-hydraulics and safety characteristics of liquid-fueled Molten Salt Reactors. Kerntechnik. 81(2016) 149-159.