Passive Cooldown Performance of Integral Pressurized Water Reactor

Shoubao  Dai; Chunnan  Jin; Jingfu  Wang; Yuxiang  Chen

doi:10.4236/epe.2013.54B097

Shoubao Dai^*, Chunnan Jin, Jingfu Wang, Yuxiang Chen

Abstract: The design of an integral pressurized water reactor (IPWR) focuses on enhancing the safety and reliability of the reactor by incorporating a number of inherent safety features and engineered safety features. However, the characteristics of passive safety systems for the marine reactors are quiet different from those for the land nuclear power plant because of the more formidable and dangerous operation environments of them. This paper presents results of marine black out accident analyses. In the case of a transient, the passive residual heat removal system (PRHRS) is designed to cool the reactor coolant system (RCS) from a normal operation condition to a hot shutdown condition by a natural circulation, and the shutdown cooling system (SCS) is designed to cool the primary system from a hot shutdown condition to a refueling condition by a forced circulation. A realistic calculation has been carried out by using the RELAP5/MOD3.4 code and a sensitivity analysis has been performed to evaluate a passive cooldown capability. The results of the accident analyses show that the reactor coolant system and the passive residual heat removal system adequately remove the core decay heat by a natural circulation.

Keywords: An Integral Pressurized Water Reactor (IPWR); Passive Safety System; Styling; Natural Circulation

Cite this paper: S. Dai, C. Jin, J. Wang and Y. Chen, "Passive Cooldown Performance of Integral Pressurized Water Reactor," Energy and Power Engineering, Vol. 5 No. 4, 2013, pp. 505-509. doi: 10.4236/epe.2013.54B097.

References

[1] Y.-J. Chung, H.-C. Kim and B.-D. Chung, “Two Phase Natural Circulation and Heat Transfer in the Passive Residual Heat Removal System of an Integral Type Reactor,” Annals of Nuclear Energy, Vol. 33, No. 3, 2006, pp. 262-270. doi:10.1016/j.anucene.2005.09.009

[2] M. H. Chang, S. K. Sim, D. J. Lee, “SMART Behavior under Over-Pressurizing Accident Conditions,” Nuclear Engineering and Design, Vol. 199, No. 1-2, 2000, pp. 187-196. doi:10.1016/S0029-5493(99)00068-0

[3] S. L. Cheng and G. J. Leng, “Inherent Safe UZrHx Power Reactor INSURE-100 Preliminary Research,” Nuclear Power Engineering, Vol. 15, No. 4, Aug. 1994.

[4] J. K. Liu and C. B. Tang, “Summarisation on Russian ABV-6M Integral Pressurized Water Reactor,” Nuclear Power Engineering, Vol. 18, No. 3,1997.

[5] Y. J. Chung, S. H. Kim and H. C. Kim, “Thermal Hydraulic Analysis of SMART for Heat Removal Transients by a Secondary System,” Nuclear Engineering and Design, 2003, pp. 225-257.

[6] Y.-J. Chung and S. W. Lee, “Passive Cooldown Performance of a 65 MW Integral Reactor,” Nuclear Engineering and Design, Vol. 238, 2008, pp. 1681-1689. doi:10.1016/j.nucengdes.2007.12.008

[7] C. D. Fletcher and R. R. Schultz. RELAP5/MOD3 Code Manual Vo-lume V: USER’ S GUIDELINES[Z], 1995, 38-42, 130-133, 139-158, 173-180.