logo

Hydrogen and steam distribution following a small-break LOCA in large dry containment

MISCELLANEOUS

Hydrogen and steam distribution following a small-break LOCA in large dry containment

DENG Jian
CAO Xuewu
Nuclear Science and TechniquesVol.18, No.3pp.181-185Published in print 20 Jun 2007
37400

The hydrogen deflagration is one of the major risk contributors to threaten the integrity of the containment in a nuclear power plant, and hydrogen control in the case of severe accidents is required by nuclear regulations. Based on the large dry containment model developed with the integral severe-accident analysis tool, a small-break loss-of-coolant-accident (LOCA) without HPI, LPI, AFW and containment sprays, leading to the core degradation and large hydrogen generation, is calculated. Hydrogen and steam distribution in containment compartments is investigated. The analysis results show that significant hydrogen deflagration risk exits in the reactor coolant pump (RCP) compartment and the cavity during the early period, if no actions are taken to mitigate the effects of hydrogen accumulation.

Severe accidentSmall-break LOCALarge dry containmentHydrogen distribution
References
[1] Alvares N J, Beason D G, Eidam G R, et al. Transactions of the American Nuclear Society, 1982, 43: 11-12.
[2] Henrie J O, Postma A K. Transactions of the American Nuclear Society, 1982, 43: 12-13.
[3] Sehgal B R. Nuclear Engineering and Design, 2001, 210: 79-94.
[4] Koroll G W, Rohde J, Royen J. Proceedings of the OECD/NEA/CSNI Workshop on the Implementation of Hydrogen Mitigation Techniques, Manitoba, Canada, May 13-15, 1996.
[5] Chen S, Liu X, Shi G. B, et al. Nuclear Power Engineering (in Chinese), 2006, 27(1): 13-17.
[6] Fang L K, Chen S, Zhou Q F. Nuclear Power Engineering (in Chinese), 2006, 27(1): 18-22.
[7] Lin J M, Jia B S, Liu B T. Nuclear Power Engineering (in Chinese), 2005, 25(3): 275-278.
[8] Lin J M, Jia B S, Liu B T. Nuclear Power Engineering (in Chinese), 2005, 26(2): 114-120.
[9] Bachellerie E, Arnould F, Auglaire M, et al. Nuclear Engineering and Design, 2003, 221: 151-165.