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宋苹
2014年9月
博二
钠冷快堆安全分析

主要研究成果

Ping Song, Dalin Zhang, S.B. Wang, et al. Numerical approach to simulate the thermo-hydraulics of Reactor Vessel Cooling System in Sodium-Cooled Fast Reactors (ICENES2017), 24-27 April 2017, Hefei, China.
2. Ping Song, Dalin Zhang, Shibao Wang, et al. Development of a One-dimensional Code for Main Vessel Cooling System of Sodium Cooled Reactors [C]. The 9th Joint International Symposium on Nuclear Science and Technology , Shanghai, China, Nov. 13-15, 2016.
3. Feng T, Wang M, Song P, et al. Thermal hydraulic characteristics analysis of direct residual heat removal system for China pressurized reactor[J]. Progress in Nuclear Energy, 2016, 93: 231-237.
4. Feng T, Zhang D, Song P, et al. Numerical research on water hammer phenomenon of parallel pump-valve system by coupling FLUENT with RELAP5[J]. Annals of Nuclear Energy, 2017, 109: 318-326.
5. Dalin Zhang, Jing Chen, Ping Song, Shibao Wang, et al. Theorectical and experimental research on the single-phase and incipient boiling heat transfer of liquid metal sodium, Proceedings of the 25th International Conference on Nuclear Engineering, May 14-18, 2017, Shanghai.
6. D.L. Zhang, P. Song, S.B. Wang, R.L. Sun, et al. Inter-Wrapper Flow Effects on Thermal-Hydraulic Characteristics of Sodium-cooled Fast Reactor under Natural Circulation Condition, The 18th International onference on Emerging Nuclear Energy Systems (ICENES2017), 24-27 April 2017, Hefei, China.
7. 冯唐涛, 田文喜, 宋苹, 等. 基于耦合程序的流体瞬变流动水锤现象分析[J]. 原子能科学技术, 2017, 51(8): 1364-1370.