[1] GAO Pengcheng, ZHANG Bin, YANG Hao et al. Development of flow blockage model for core heat transfer and its application in QUENCH experiment[J]. Nuclear Techniques, 46, 070606(2023).

[2] Cadek F F, Dominicis D P, Leyse R H. PWR flecht: (full length emergency cooling heat transfer). final report[R]. WCAP-7665(1971).

[3] Grutter H, Aksan S N. NEPTUN bundle reflooding experiments: test facility description[R]. EIR-Bericht 386(1980).

[4] Cho S, Moon S K, Choi K Y et al. Rewetting of vertical hot surface in a centrally heated annulus and a 6×6 rod bundle geometry during reflood phase[C], 415-422(2008).

[5] SHI Mingzhe, XU Guohua. The reflooding heat transfer experimenm in rod boundle[J]. Atomic Energy Science and Technology, 27, 348-352(1993).

[6] HUANG Yanping, LANG Xuemei. Correlation of heat transfer coefficientfor quench front[J]. Nuclear Power Engineering, 19, 138-143(1998).

[7] JI Jianye, XU Wei, CHAI Xiang et al. Experimental investigation and CFD simulation of reflooding in narrow rectangle channel[J]. Nuclear Techniques, 40, 010601(2017).

[8] CHEN Yuzhou, YANG Chunsheng, ZOU Ling. An evaluation of RELAP5 based on the CIAE experiments[J]. Nuclear Power Engineering, 24, 64-69(2003).

[9] Yuan J T, Tong L L, Cao X W. Simulation of quenching in horizontal geometry channel[J]. Nuclear Science and Techniques, 21, 370-374(2010).

[10] Nilsson L. Assessment of RELAP5/MOD3 against twenty-five post-dryout experiments performed at the Royal Institute of Technology[R]. NUREG/IA-0094(1993).

[11] Analytis G T. Study of the post-CHF wall heat transfer package of RELAP5/MOD3.3 during blow-down[J]. Annals of Nuclear Energy, 31, 1053-1068(2004).

[12] Choi T S, No H C. An improved RELAP5/MOD3.3 reflood model considering the effect of spacer grids[J]. Nuclear Engineering and Design, 250, 613-625(2012).

[13] Zeng W. Research on characteristic of the inverted annular flow regime during the narrow channel[C](2011).

[14] Coleman H W, Steele W G. Engineering application of experimental uncertainty analysis[J]. AIAA Journal, 33, 1888-1896(1995).

[15] Monde M. Analytical method in inverse heat transfer problem using Laplace transform technique[J]. International Journal of Heat and Mass Transfer, 43, 3965-3975(2000).

[16] Jin Y, Cheung F B, Bajore S M K et al. Investigation of the thermal-hydraulic non-equilibrium in a 7×7 rod bundle during reflood[J]. International Journal of Heat and Mass Transfer, 127, 266-279(2018).

[17] Mohanta L. Theoretical and experimental study of inverted annular film boiling and regime transition during reflood transients[D](2015).

[18] Wang Z F, Zhong M, Deng J et al. Experimental investigation on the transient film boiling heat transfer during quenching of FeCrAl[J]. Annals of Nuclear Energy, 150, 107842(2021).

[19] Cao C Q, Kuang B, Zha Y et al. A relatively wide-ranged correlation of saturated flow boiling heat transfer within narrow rectangular channel for water[J]. Applied Thermal Engineering, 210, 118345(2022).

[20] Osakabe M, Sudo Y. Heat transfer calculation of simulated heater rods throughout reflood phase in postulated PWR-LOCA experiments[J]. Journal of Nuclear Science & Technology, 20, 559-570(2008).

[21] Xiong J B, Wang Z F, Xiong P et al. Experimental investigation on transient boiling heat transfer during quenching of fuel cladding surfaces[J]. International Journal of Heat and Mass Transfer, 148, 119131(2020).