NUCLEAR TECHNIQUES, Volume. 45, Issue 10, 100604(2022)
A new CHF mechanism model for a narrow rectangular channel based on bubble dynamics characteristics
[1] PAN Liangming[M]. Thermal hydraulic fundamentals of nuclear reactors, 97-111(2020).
[2] Ishii M, Hibiki T. Two-fluid model[M]. Thermo-Fluid Dynamics of Two-Phase Flow, 155-216(2010).
[3] Liu P, Guo Y S, Ding W L et al. Critical heat flux (CHF) correlations for subcooled water flow boiling at high pressure and high heat flux[J]. Journal of Thermal Science, 30, 279-293(2021).
[4] Song J H, Jung J Y, Chang S H et al. Mechanistic CHF model development for subcooled flow boiling in a vertical rectangular channel under low pressure[J]. International Journal of Heat and Mass Transfer, 174, 121328(2021).
[5] Yang B W, Han B, Liu A G et al. Recent challenges in subchannel thermal-hydraulics-CFD modeling, subchannel analysis, CHF experiments, and CHF prediction[J]. Nuclear Engineering and Design, 354, 110236(2019).
[6] Tong L S. Boundary-layer analysis of the flow boiling crisis[J]. International Journal of Heat and Mass Transfer, 11, 1208-1211(1968).
[7] Weisman J, Pei B S. Prediction of critical heat flux in flow boiling at low qualities[J]. International Journal of Heat and Mass Transfer, 26, 1463-1477(1983).
[8] Katto Y. Prediction of critical heat flux of subcooled flow boiling in round tubes[J]. International Journal of Heat and Mass Transfer, 33, 1921-1928(1990).
[9] Galloway J E, Mudawar I. CHF mechanism in flow boiling from a short heated wall-II. Theoretical CHF model[J]. International Journal of Heat and Mass Transfer, 36, 2527-2540(1993).
[10] Bruder M, Bloch G, Sattelmayer T. Critical heat flux in flow boiling-review of the current understanding and experimental approaches[J]. Heat Transfer Engineering, 38, 347-360(2017).
[11] Le Corre J M, Yao S C, Amon C H. Two-phase flow regimes and mechanisms of critical heat flux under subcooled flow boiling conditions[J]. Nuclear Engineering and Design, 240, 245-251(2010).
[12] Bricard B, Peturaud P, Delhaye J M. Understanding and modelling DNB in forced convective boiling: modelling of a mechanism based on nucleation site dryout[J]. Multiphase Science and Technology, 9, 329-379(1997).
[13] Ha S J, No H C. A dry-spot model of critical heat flux applicable to both pool boiling and subcooled forced convection boiling[J]. International Journal of Heat and Mass Transfer, 43, 241-250(2000).
[14] Zhao Y H, Masuoka T, Tsuruta T. Unified theoretical prediction of fully developed nucleate boiling and critical heat flux based on a dynamic microlayer model[J]. International Journal of Heat and Mass Transfer, 45, 3189-3197(2002).
[15] Luitjens J, Wu Q, Greenwood S et al. Mechanistic CHF modeling for natural circulation applications in SMR[J]. Nuclear Engineering and Design, 310, 604-611(2016).
[16] Ding W, Geißler T, Krepper E et al. Critical heat flux as a mass flux dependent local or global phenomenon: theoretical analysis and experimental confirmation[J]. International Journal of Thermal Sciences, 130, 200-207(2018).
[17] Kaminaga M, Yamamoto K, Sudo Y. Improvement of critical heat flux correlation for research reactors using plate-type fuel[J]. Journal of Nuclear Science and Technology, 35, 943-951(1998).
[18] Chen D Q, Pan L M, Yuan D W et al. Dual model of bubble growth in vertical rectangular narrow channel[J]. International Communications in Heat and Mass Transfer, 37, 1004-1007(2010).
[19] XU Jianjun, CHEN Bingde, WANG Xiaojun. Study on bubble growth and departure near wall in vertical narrow rectangular channel[J]. Atomic Energy Science and Technology, 44, 1349-1354(2010).
[20] Okawa T, Ishida T, Kataoka I et al. An experimental study on bubble rise path after the departure from a nucleation site in vertical upflow boiling[J]. Experimental Thermal and Fluid Science, 29, 287-294(2005).
[21] Okawa T, Ishida T, Kataoka I et al. Bubble rise characteristics after the departure from a nucleation site in vertical upflow boiling of subcooled water[J]. Nuclear Engineering and Design, 235, 1149-1161(2005).
[22] YAN Meiyue. Experimental study of wall heat flux partitioning model in vertical rectangular narrow channel[D](2019).
[23] Xu J J, Chen B D, Huang Y P et al. Experimental visualization of sliding bubble dynamics in a vertical narrow rectangular channel[J]. Nuclear Engineering and Design, 261, 156-164(2013).
[24] LI Shaodan. Study of local bubble behavior and boiling heat transfer characteristics under ocean condition[D](2015).
[25] Le Corre J M, Yao S C, Amon C H. A mechanistic model of critical heat flux under subcooled flow boiling conditions for application to one- and three-dimensional computer codes[J]. Nuclear Engineering and Design, 240, 235-244(2010).
[26] Ding W, Krepper E, Hampel U. Quantitative prediction of critical heat flux initiation in pool and flow boiling[J]. International Journal of Thermal Sciences, 125, 121-131(2018).
[27] Sudo Y, Kaminaga M. A CHF characteristic for downward flow in a narrow vertical rectangular channel heated from both sides[J]. International Journal of Multiphase Flow, 15, 755-766(1989).
[28] Sudo Y. Study on critical heat flux in rectangular channels heated from one or both sides at pressures ranging from 0.1 to 14 MPa[J]. Journal of Heat Transfer, 118, 680-688(1996).
[29] Yan M Y, Yang Y Y, Ren T T et al. Characteristics of sliding bubbles in subcooled flow boiling in a narrow rectangular channel under natural circulation condition[J]. International Journal of Heat and Mass Transfer, 144, 118587(2019).
[30] Yan M Y, Ren T T, Chen K L et al. Visualized experiment of bubble behaviors in a vertical narrow rectangular channel under natural circulation condition[J]. Frontiers in Energy Research, 6, 105(2018).
[31] del Valle V H, Kenning D B R. Subcooled flow boiling at high heat flux[J]. International Journal of Heat and Mass Transfer, 28, 1907-1920(1985).
[32] Gnielinski V. New equations for heat and mass transfer in the turbulent flow in pipes and channels[R]. NASA STI/recon Technical Report A(1975).
[33] Zeitoun O, Shoukri M. Bubble behavior and Mean diameter in subcooled flow boiling[J]. Journal of Heat Transfer, 118, 110-116(1996).
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Meiyue YAN, Liangming PAN, Zaiyong MA, Xiang LI, Lingfeng WAN. A new CHF mechanism model for a narrow rectangular channel based on bubble dynamics characteristics[J]. NUCLEAR TECHNIQUES, 2022, 45(10): 100604
Category: Research Articles
Received: Mar. 10, 2022
Accepted: --
Published Online: Nov. 4, 2022
The Author Email: PAN Liangming (cneng@cqu.edu.cn)