Citation: | Sun Yuanli, Song Zhihao, Lyu Xiangbo. Research on Simulation Model of Small Integrated Lead-Bismuth Cooled Reactor[J]. Nuclear Power Engineering, 2023, 44(6): 193-198. doi: 10.13832/j.jnpe.2023.06.0193 |
[1] |
ZRODNIKOV A V, TOSHINSKY G I, KOMLEV O G, et al. Nuclear power development in market conditions with use of multi-purpose modular fast reactors SVBR-75/100[J]. Nuclear Engineering and Design, 2006, 236(14-16): 1490-1502. doi: 10.1016/j.nucengdes.2006.04.005
|
[2] |
GREENSPAN E, HONG S G, LEE K B, et al. Innovations in the ENHS reactor design and fuel cycle[J]. Progress in Nuclear Energy, 2008, 50(2-6): 129-139. doi: 10.1016/j.pnucene.2007.10.022
|
[3] |
TAKAHASHI M, UCHIDA S, HATA K, et al. Pb-Bi-cooled direct contact boiling water small reactor[J]. Progress in Nuclear Energy, 2005, 47(1-4): 190-201. doi: 10.1016/j.pnucene.2005.05.020
|
[4] |
CHOI S, HWANG I S, CHO J H, et al. URANUS: Korean lead-bismuth cooled small modular fast reactor activities[C]//ASME 2011 Small Modular Reactors Symposium. Washington: ASME, 2011: 107-112.
|
[5] |
WU Y C. Design and R&D progress of china lead-based reactor for ADS research facility[J]. Engineering, 2016, 2(1): 124-131. doi: 10.1016/J.ENG.2016.01.023
|
[6] |
GUO C, ZHAO P C, DENG J, et al. Safety analysis of small modular natural circulation lead-cooled fast reactor SNCLFR-100 under unprotected transient[J]. Frontiers in Energy Research, 2021, 9: 678939. doi: 10.3389/fenrg.2021.678939
|
[7] |
SUVDANTSETSEG E. Neutronics and transient analysis of a small fast reactor cooled with natural circulation of lead: ELECTRA: European lead cooled training reactor[D]. Stockholm: KTH Royal Institute of Technology, 2014.
|
[8] |
YAN M Y, SEKIMOTO H. Safety analysis of small long life CANDLE fast reactor[J]. Annals of Nuclear Energy, 2008, 35(5): 813-828. doi: 10.1016/j.anucene.2007.09.009
|
[9] |
WEI S Y, MA W M, WANG C L, et al. Development and validation of transient thermal-hydraulic evaluation code for a lead-based fast reactor[J]. International Journal of Energy Research, 2021, 45(8): 12215-12233. doi: 10.1002/er.6334
|
[10] |
YANG Y P, WANG C L, ZHANG D L, et al. Numerical analysis of liquid metal helical coil once-through tube steam generator[J]. Annals of Nuclear Energy, 2022, 167: 108860. doi: 10.1016/j.anucene.2021.108860
|
[11] |
HERNANDEZ C R, GRISHCHENKO D, KUDINOV P, et al. Development of a CFD-based model to simulate loss of flow transients in a small lead-cooled reactor[J]. Nuclear Engineering and Design, 2022, 392: 111773. doi: 10.1016/j.nucengdes.2022.111773
|
[12] |
FAZIO C. Handbook on lead-bismuth eutectic alloy and lead properties, materials compatibility, thermal-hydraulics and technologies[R]. Paris: OECD, 2015.
|
[13] |
MIKITYUK K. Heat transfer to liquid metal: Review of data and correlations for tube bundles[J]. Nuclear Engineering and Design, 2009, 239(4): 680-687. doi: 10.1016/j.nucengdes.2008.12.014
|
[14] |
CHENG X, BATTA A, CHEN H Y, et al. Turbulent heat transfer to heavy liquid metals in circular tubes[C]//ASME 2004 Heat Transfer/Fluids Engineering Summer Conference. Charlotte: ASME, 2004: 115-125.
|
[15] |
XIA G L, YUAN Y, PENG M J, et al. Numerical studies of a helical coil once-through steam generator[J]. Annals of Nuclear Energy, 2017, 109: 52-60. doi: 10.1016/j.anucene.2017.05.025
|
[16] |
李精精,周涛,刘梦影,等. 铅铋与水自然循环流动传热比较分析[J]. 核科学与工程,2014, 34(2): 249-256.
|
[17] |
CHENG S K, TODREAS N E. Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles—Bundle friction factors, subchannel friction factors and mixing parameters[J]. Nuclear Engineering and Design, 1986, 92(2): 227-251. doi: 10.1016/0029-5493(86)90249-9
|