Citation: | Liu Songyang, Wang Lang, Li Xuelin, Guo Ruonan, Liu wei, Luo Yong, Zhou Qin. Preliminary Study on 950℃ Coolant Outlet Temperature in HTR-PM under the OTTO Scheme[J]. Nuclear Power Engineering, 2025, 46(S1): 41-51. doi: 10.13832/j.jnpe.2025.S1.0041 |
[1] |
KUGELER K, ZHANG Z Y. Modular high-temperature gas-cooled reactor power plant[M]. Berlin Heidelberg: Springer, 2019: 85-86.
|
[2] |
SHE D, GUO J, LIU Z H, et al. PANGU code for pebble-bed HTGR reactor physics and fuel cycle simulations[J]. Annals of Nuclear Energy, 2019, 126: 48-58. doi: 10.1016/j.anucene.2018.11.005
|
[3] |
RÜTTEN H J, HAAS K A, POHL C. Computer code system V. S. O. P. (99/11) update 2011 of V. S. O. P(99)-version 2009 code manual: Jul-4348[R]. Jül-4348, Bundesrepublik Deutschland: Forschungszentrum Jülich, 2012.
|
[4] |
CHEN F B, HAN Z H. Steady-state thermal fluids analysis for the HTR-PM equilibrium core[J]. International Journal of Advanced Nuclear Reactor Design and Technology, 2021, 3: 11-17. doi: 10.1016/j.jandt.2021.04.001
|
[5] |
ZHENG Y H, SHI Y, DONG Y J. Thermohydraulic transient studies of the Chinese 200 MWe HTR-PM for loss of forced cooling accidents[J]. Annals of Nuclear Energy, 2009, 36(6): 742-751. doi: 10.1016/j.anucene.2009.02.007
|