Since the Fukushima accident in 2011, more and more attention has been paid to nuclear reactor safety. A number of evolutionary passive systems have been developed to enhance the inherent safety of reactors. This paper presents a passive safety system applied on CPR1000, which is a traditional generation II+ reactor. The passive components selected are as follows: (1) the reactor makeup tanks (RMTs); (2) the advanced accumulators (A-ACCs); (3) the passive emergency feedwater system (PEFS); (4) the passive depressurization system (PDS); (5) the in-containment refueling water storage tank (IRWST). The model of the coolant system and the passive systems was established by utilizing a system code (RELAP5/MOD3.3). The SBLOCA (small-break loss of coolant) was analyzed to test the passive safety systems. When the SBLOCA occurred, the RMTs were initiated. The water in the RMTs was then injected into the pressure vessel. The RMTs’ low water level triggered the PDS, which depressurized the coolant system drastically. As the pressure of the coolant system decreased, the A-ACCs and the IRWST were put to work to prevent the uncovering of the core. The results show that, after the small-break loss-of-coolant accident, the passive systems can prevent uncovering of the core and guarantee the safety of the plant.
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Z.J. Xiao, W.B. Zhou, H. Zheng et al., Experimental research progress on passive safety systems of Chinese advanced PWR. Nucl. Eng. Des. 225, 305–313 (2003). doi:10.1016/S0029-5493(03)00178-X
P.E. Juhn, J. Kupitz, J. Cleveland et al., IAEA activities on passive safety systems and overview of international development. Nucl. Eng. Des. 201, 41–59 (2000). doi:10.1016/S0029-5493(00)00260-0
A.K. Nayak, R.K. Sinha, Role of passive systems in advanced reactors. Prog. Nucl. Energy 49, 486–498 (2007). doi:10.1016/j.pnucene.2007.07.007
A.K. Nayak, A. Chandrakar, G. Vinod, A review: passive system reliability analysis–accomplishments and unresolved issues. Front. Energy Reasear 2, 40 (2014). doi:10.3389/fenrg.2014.00040
B.T. Timofeev, G.P. Karzov, Assessment of the WWER-1000 reactor condition. Int. J. Pres Vessels Pip. 83, 464–473 (2006). doi:10.1016/j.ijpvp.2005.11.008
M.D. Carelli, L.E. Conway, L. Oriani et al., The design and safety features of the IRIS reactor. Nucl. Eng. Des. 230, 151–167 (2004). doi:10.1016/j.nucengdes.2003.11.022
K.H. Bae, H.C. Kim, M.H. Chang et al., Safety evaluation of the inherent and passive safety features of the smart design. Ann. Nucl. Energy 28, 333–349 (2001). doi:10.1016/S0306-4549(00)00057-8
B. Sutharshan, M. Mutyala, R.P. Vijuk et al., The AP1000TM reactor: passive safety and modular design. Energy Procedia 7, 293–302 (2011). doi:10.1016/j.egypro.2011.06.038
Y. Tujikura, T. Oshibe, K. Kijima et al., Development of passive safety systems for Next Generation PWR in Japan. Nucl. Eng. Des. 201, 61–70 (2000). doi:10.1016/S0029-5493(00)00261-2
I.-C. Chu, C.-H. Song, B.H. Cho et al., Development of passive flow controlling safety injection tank for APR1400. Nucl. Eng. Des. 238, 200–206 (2008). doi:10.1016/j.nucengdes.2007.07.002
H. Hu, J. Shan, J. Gou et al., Simulation of advanced accumulator and its application in CPR1000 LBLOCA analysis. Ann. Nucl. Energy 69, 183–195 (2014). doi:10.1016/j.anucene.2014.01.037
Y. Zhang, S. Qiu, G. Su et al., Design and transient analyses of emergency passive residual heat removal system of CPR1000. Part I: air cooling condition. PROG NUCL. ENERG 53, 471–479 (2011). doi:10.1016/j.pnucene.2011.03.001
J. Wu, Q. Bi, C. Zhou, Experimental study on circulation characteristics of secondary passive heat removal system for Chinese pressurized water reactor. Appl. Therm. Eng. 77, 106–112 (2015). doi:10.1016/j.applthermaleng.2014.12.014
J. Wu, Q. Bi, C. Zhou, American Society of mechanical engineers: experimental investigations on temperature distribution and heat removal capability of residual heat exchanger, ASME 2013 Power Conference, 2013
M. Gavrilas, N.E. Todreas, M.J. Driscoll, Containment passive-cooling design concepts. Prog. Nucl. Energy 32, 647–655 (1998). doi:10.1016/S0149-1970(97)00069-3
S.H. Chang, S.H. Kim, J.Y. Choi, Design of integrated passive safety system (IPSS) for ultimate passive safety of nuclear power plants. Nucl. Eng. Des. 260, 104–120 (2013). doi:10.1016/j.nucengdes.2013.03.018
A. Achilli, G. Cattadori, R. Ferri et al., Two new passive safety systems for LWR applications. Nucl. Eng. Des. 200, 383–396 (2000). doi:10.1016/S0029-5493(00)00256-9
C.S. Byun, D.W. Jerng, N.E. Todreas et al., Conceptual design and analysis of a semi-passive containment cooling system for a large concrete containment. Nucl. Eng. Des. 199, 227–242 (2000). doi:10.1016/S0029-5493(00)00228-4
M. Gavrilas, N.E. Todreas, M.J. Driscoll, The design and evaluation of a passively cooled containment for a high-rating pressurized water reactor. Nucl. Eng. Des. 200, 233–249 (2000). doi:10.1016/S0029-5493(99)00339-8
M. Hashim, H. Yoshikawa, T. Matsuoka et al., Quantitative dynamic reliability evaluation of AP1000 passive safety systems by using FMEA and GO-FLOW methodology. J. Nucl. Sci. Technol. 51, 526–542 (2014). doi:10.1080/00223131.2014.881727
A.C.F. Guimarães, C.M.F. Lapa, F.F.L.S. Filho et al., Fuzzy uncertainty modeling applied to AP1000 nuclear power plant LOCA. Ann. Nucl. Energy 38, 1775–1786 (2011). doi:10.1016/j.anucene.2011.02.005
M. Hashim, Y. Hidekazu, M. Takeshi et al., Application case study of AP1000 automatic depressurization system (ADS) for reliability evaluation by GO-FLOW methodology. Nucl. Eng. Des. 278, 209–221 (2014). doi:10.1016/j.nucengdes.2014.06.040
China Nuclear Power Technology Research Institution, Final Safety Analysis Report (FSAR) of Ling’ao Nuclear Power Plant Phase 2161,CGNPC CHN, 2008
This work was supported by the National High-tech R&D Program of China (No. 2012AA050905).
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Yang, ZJ., Gou, JL., Shan, JQ. et al. Analysis of SBLOCA on CPR1000 with a passive system. NUCL SCI TECH 28, 10 (2017). https://doi.org/10.1007/s41365-016-0154-y
- Passive safety systems