[2] CAO Kemei, XU Yiquan, SHI Guobao et al. ERVC effectiveness analysis for three-layer configuration molten pool[J]. Nuclear Power Engineering, 34, 20-22, 94(2013).

[3] CAO Zhen, CAO Kemei, WANG Jiayun. Uncertainty analysis of in vessel retention in three-layer melt pool configuration[J]. Nuclear Techniques, 41, 100605(2018).

[4] SHI Xingwei, LAN Bing, BI Jinsheng et al. Effect of concrete type on containment during MCCI process[J]. Nuclear Techniques, 41, 040603(2018).

[5] SHI Xingwei, SHI Qiang, MA Guoqiang et al. Sensitivity analysis of the hydrogen mole fraction limit for ignition with MELCOR2.2[J]. Nuclear Techniques, 42, 050601(2019).

[6] Carénini L, Fichot F. The impact of transient behavior of corium in the lower head of a reactor vessel for In-vessel melt retention strategies[C].

[7] Zhang Y P, Qiu S Z, Su G H et al. A simple novel analysis procedure for IVR calculation in core-molten severe accident[J]. Nuclear Engineering and Design, 241, 4634-4642(2011).

[8] GUO Tao, BAO Shiyi, GAO Zengliang. Numerical calculation on steady temperature field of reactor pressure vessel under severe accident conditions in- vessel retention[J]. Pressure Vessel Technology, 29, 34-39, 73(2012).

[9] JIN Yue. IVR-ERVC effectiveness assessment for large scale pressurized water reactor under severe accident using MELCOR[D](2014).

[10] XIANG Qingan, GUAN Zhonghua, DENG Chunrui et al. An assessment methodology of thee-layers melt configuration during IVR for AP1000[J]. Nuclear Power Engineering, 34, 83-87(2013).

[11] Chatelard P, Reinke N, Arndt S et al. ASTEC V2 severe accident integral code main features, current V2.0 modelling status, perspectives[J]. Nuclear Engineering and Design, 272, 119-135(2014).

[12] Chatelard P, Chikhi N, Cloarec L et al. ASTEC V2 code ICARE physical modeling, IRSN/DPAM/SEMCA/2009-148[R](2009).

[13] Piar L, Trégourès N, Moal A. ASTEC V2 code: CESAR physical and numerical modelling[R]. IRSN/DPAM/SEMCA/2010-380(2010).

[14] Gabor J D. Heat transfer to particle beds with gas flows less than or equal to that required for incipient fluidization[J]. Chemical Engineering Science, 25, 979-984(1970).

[15] SONG Wei, ZHOU Kefeng, ZHENG Peng et al. Influence of corium configuration on heat transfer calculation of RPV lower head with ASTEC code[J]. Atomic Energy Science and Technology, 51, 1785-1790(2017).

[16] Hu Q, Yan X, Huang S F et al. The comprehensive analysis of coolability limits of passive external reactor vessel cooling under in-vessel retention[J]. Annals of Nuclear Energy, 120, 296-303(2018).

[17] Guo R, Kuang B, Cheng X. A theoretical CHF model for subcooled flow boiling in curved a channel at low pressure[J]. Annals of Nuclear Energy, 69, 196-202(2014).

[18] Park H M, Jeong Y H, Heo S. Effect of heater material and coolant additives on CHF for a downward facing curved surface[J]. Nuclear Engineering and Design, 278, 344-351(2014).

[19] Sanchez F, Zambaux J A, Giordano P et al. Draft manual for ASTEC V2.1: CESAR module user manual[R](2018).