[2] Keller F R. Fuel element flow blockage in the engineering test react[R]. IDO16780, 1962.
[3] Sims T M, Tab W H. Rept on fuelplate melting at the Oak Ridge Research React[R]. NLTM627, 1964.
[4] Adorni M, Bousbia-Salah A, Hamidouche T, et al. Analysis of partial and total flow blockage of a single fuel assembly of an MTR research reactor core[J]. Annals of Nuclear Energy, 32, 1679-1692(2005).
[6] Guo Yuchuan, Wang Guanbo, Qian Dazhi, et al. Thermal hydraulic analysis of loss of flow accident in the JRR-3M research reactor under the flow blockage transient[J]. Annals of Nuclear Energy, 118, 147-153(2018).
[7] Guo Yuchuan, Wang Guanbo, Qian Dazhi, et al. Transient thermal-hydraulic analysis of single flow channel blockage in the JRR-3M 20-MW research reactor[J]. Nuclear Technology, 204, 15-24(2018).
[8] Guo Yuchuan. Analysis of plate fuel element react channel blockage accident[D]. Mianyang: China Academy of Engineering Physics, 2019: 3742
[9] Song Lei. Numerical analysis of the flow blockage accidents in platetype fuel assembly[D]. Harbin: Harbin Engineering University, 2013: 812
[10] Salama A, El-Morshed S E D. CFD simulation of flow blockage through a coolant channel of a typical material testing reactor core[J]. Annals of Nuclear Energy, 41, 26-39(2012).
[11] Salama A. CFD investigation of flow inversion in typical MTR research reactor undergoing thermal–hydraulic transients[J]. Annals of Nuclear Energy, 38, 1578-1592(2011).
[12] Salama A, El-Morshedy S E D. CFD analysis of flow blockage in MTR coolant channel under loss-of-flow transient: hot channel scenario[J]. Progress in Nuclear Energy, 55, 78-92(2012).
[13] Albati M A, Al-Yahia O S, Park J, et al. Thermal hydraulic analyses of JRR-3: Code-to-code comparison of COOLOD-N2 and TMAP[J]. Progress in Nuclear Energy, 71, 1-8(2014).
[14] Han Hua. Experimental study on thermal stability of diffuse fuel element[D]. Beijing: China Institute of Atomic Energy, 2003: 13