Citation: | Zhang Zhenguo, Tan Sichao, Li Xiaochang, Liu Sichao, Feng Yi, Huang Yujian, Tian Ruifeng. Numerical Simulation Method of Boiling Heat Transfer and Its Application Characteristics under Multi-tube Coupled Heat Transfer[J]. Nuclear Power Engineering, 2024, 45(2): 130-138. doi: 10.13832/j.jnpe.2024.02.0130 |
[1] |
孙中宁,阎昌琪. 核动力设备[M]. 哈尔滨: 哈尔滨工程大学出版社,2004: 20-23.
|
[2] |
王冲. 中国实验快堆蒸汽发生器稳态特性分析及热工水力设计[D]. 大连: 大连理工大学,2013.
|
[3] |
CONG T L, TIAN W X, QIU S Z, et al. Study on secondary side flow of steam generator with coupled heat transfer from primary to secondary side[J]. Applied Thermal Engineering, 2013, 61(2): 519-530. doi: 10.1016/j.applthermaleng.2013.08.024
|
[4] |
干依燃,孙宝芝,齐洪亮,等. 基于传热分区的直流蒸汽发生器换热性能仿真[J]. 化工学报,2015, 66(Z1): 123-129.
|
[5] |
张振国,李小畅,谭思超,等. 钠冷快堆直流蒸汽发生器跨尺度耦合分析[J]. 原子能科学技术,2022, 56(11): 2354-2364.
|
[6] |
TALEBI S, KAZEMINEJAD H, DAVILU H. Prediction of dryout and post-dryout wall temperatures using film thickness model[J]. Nuclear Engineering and Design, 2012, 244: 73-82. doi: 10.1016/j.nucengdes.2011.12.032
|
[7] |
LI H P, ANGLART H. Prediction of dryout and post-dryout heat transfer using a two-phase CFD model[J]. International Journal of Heat and Mass Transfer, 2016, 99: 839-850. doi: 10.1016/j.ijheatmasstransfer.2016.04.021
|
[8] |
ZHANG H B, HEWITT G F. Phenomenological modelling of CHF in annular flow in annuli using new models of droplet deposition and entrainment[J]. Nuclear Engineering and Design, 2016, 305: 284-292. doi: 10.1016/j.nucengdes.2016.05.029
|
[9] |
ZHANG R, CONG T L, TIAN W X, et al. Prediction of CHF in vertical heated tubes based on CFD methodology[J]. Progress in Nuclear Energy, 2015, 78: 196-200. doi: 10.1016/j.pnucene.2014.10.001
|
[10] |
MALI C R, VINOD V, PATWARDHAN A W. Comparison of phase interaction models for high pressure subcooled boiling flow in long vertical tubes[J]. Nuclear Engineering and Design, 2017, 324: 337-359. doi: 10.1016/j.nucengdes.2017.09.010
|
[11] |
MALI C R, VINOD V, PATWARDHA A W. New methodology for modeling pressure drop and thermal hydraulic characteristics in long vertical boiler tubes at high pressure[J]. Progress in Nuclear Energy, 2019, 113: 215-229. doi: 10.1016/j.pnucene.2019.01.026
|
[12] |
SHI J X, SUN B Z, ZHANG G L, et al. Prediction of dryout and post-dryout wall temperature at different operating parameters for once-through steam generators[J]. International Journal of Heat and Mass Transfer, 2016, 103: 66-76. doi: 10.1016/j.ijheatmasstransfer.2016.07.027
|
[13] |
KURUL N, PODOWSKI M Z. On the modeling of multidimensional effects in boiling channels[C]//27th National Heat Transfer Conference. Minneapolis, Minnesota, USA: ANS, 1991: 28-31.
|
[14] |
IOILEV A, SAMIGULIN M, USTINENKO V, et al. Advances in the modeling of cladding heat transfer and critical heat flux in boiling water reactor fuel assemblies[C]//Proceedings of 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-12). US: Pittsburgh, 2007: 1-16.
|
[15] |
李小畅,郜冶. 压水堆子通道欠热沸腾数值验证及交混翼研究[J]. 原子能科学技术,2013, 47(12): 2208-2215.
|
[16] |
李小畅. 棒束通道单相及两相流动与传热数值研究[D]. 哈尔滨: 哈尔滨工程大学,2015.
|
[17] |
霍飞鹏,陈纲,丁炜堃,等. 用CFD方法评价低压过冷沸腾相间传递模型[J]. 高技术通讯,2015, 25(7): 734-745.
|
[18] |
DE BERTODANO L. Turbulent bubbly two-phase flow in a triangular duct[D]. Troy: Rensselaer Polytechnic Institute, 1991.
|
[19] |
ANTAL S P, LAHEY R T JR, FLAHERTY J E. Analysis of phase distribution in fully developed laminar bubbly two-phase flow[J]. International Journal of Multiphase Flow, 1991, 17(5): 635-652. doi: 10.1016/0301-9322(91)90029-3
|
[20] |
BECKER K M, LING C H, HEDBERG S, et al. An experimental investigation of post dryout heat transfer: KTH-NEL-33[R]. Sweden: Dept. of Reactor Technology, 1983.
|
[21] |
MURALLIDHARAN J S, PRASAD B V S S S, PATNAIK B S V, et al. CFD investigation and assessment of wall heat flux partitioning model for the prediction of high pressure subcooled flow boiling[J]. International Journal of Heat and Mass Transfer, 2016, 103: 211-230. doi: 10.1016/j.ijheatmasstransfer.2016.06.050
|
[22] |
EGOROV Y, MENTER F. Experimental Implementation of the RPI Wall Boiling Model in CFX-5.6: TR-04-10[R]. Pennsylvania: ANSYS GmbH, 2004.
|
[23] |
NANDAKUMAR R, SELVARAJ P, ATHMALINGAM S, et al. Thermal simulation of sodium heated once through steam generator for a fast reactor[J]. International Journal of Advances in Engineering Sciences and Applied Mathematics, 2012, 4(3): 127-137. doi: 10.1007/s12572-012-0063-1
|
[24] |
VINOD V, SIVAKUMAR L S, KUMAR V A S, et al. Experimental evaluation of the heat transfer performance of sodium heated once through steam generator[J]. Nuclear Engineering and Design, 2014, 273: 412-420. doi: 10.1016/j.nucengdes.2014.03.034
|