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Performance analysis of the passive safety features of iPOWER under Fukushima-like accident conditions

  • Kang, Sang Hee (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • Lee, Sang Won (Korea Hydro&Nuclear Power Co., Ltd) ;
  • Kang, Hyun Gook (Department of Mechanical, Aerospace and Nuclear Engineering, Rensselaer Polytechnic Institute)
  • 투고 : 2018.09.29
  • 심사 : 2018.11.20
  • 발행 : 2019.04.25

초록

After the Fukushima Daiichi accident, there has been an increasing preference for passive safety features in the nuclear power industry. Some passive safety systems require limited active components to trigger subsequent passive operation. Under very serious accident conditions, passive safety features could be rendered inoperable or damaged. This study evaluates (i) the performance and effectiveness of the passive safety features of iPOWER (innovative Power Reactor), and (ii) whether a severe accident condition could be reached if the passive safety systems are damaged, namely the case of heat exchanger tube rupture. Analysis results show that the reactor coolant system remains in the hot shutdown condition without operator actions or electricity for over 72 h when the passive auxiliary feedwater systems (PAFSs) are operable without damage. However, heat exchanger tube rupture in the PAFS leads to core damage after about 18 h. Such results demonstrate that, to enhance the safety of iPOWER, maintaining the integrity of the PAFS is critical, and therefore additional protections for PAFS are necessary. To improve the reliability of iPOWER, additional battery sets are necessary for the passive safety systems using limited active components for accident mitigation under such extreme circumstances.

키워드

참고문헌

  1. Korea Hydro & Nuclear Power Co, APR+ Standard Safety Analysis Report, Korea Hydro & Nuclear Power Co., Daejeon, 2014.
  2. J. Xing, D. Song, Y. Wu, HPR1000: advanced pressurized water reactor with active and passive safety, Engineering 2 (1) (2016) 79-87. https://doi.org/10.1016/J.ENG.2016.01.017
  3. H.K. Sun Heo, Passive Safety Concept for Innovative Safety Plant, The Korean society for energy, 2016.
  4. IAEA. (1991). Safety Related Terms for Advanced Nuclear Plants. Iaea-Tecdoc-626, (September), 20
  5. PAFS-system Functional Description [9-454-N403-001(REV.2)], Korea Hydro & Nuclear Power Co., Daejeon (2014)
  6. S. Il Chung, S.J. Hong, S.H. Kang, H.G. Kim, S. Korea, K. Hydro, S. Korea, Analysis for Conceptual Design Combination of Passive Emergency Core Cooling System, 2014, pp. 29-30.
  7. T.L. Schulz, Westinghouse AP1000 advanced passive plant, Nucl. Eng. Des. 236 (14-16) (2006) 1547-1557. https://doi.org/10.1016/j.nucengdes.2006.03.049
  8. J. Yang, R. Liang, Z. Lin, X. Huang, T. Wang, Transient analysis of AP1000 NPP under the similar Fukushima accident conditions, Ann. Nucl. Energy 108 (2017) 181-187. https://doi.org/10.1016/j.anucene.2017.04.026
  9. S.W. Lee, S. Heo, H.U. Ha, H.G. Kim, The Concept of the Innovative Power Reactor, Nuclear Engineering and Technology, 2017.
  10. Westinghouse, AP1000 Overview (Westinghouse Non-proprietary Class 3), 2011, pp. 1-41.
  11. J. Montero-Mayorga, C. Queral, J. Gonzalez-Cadelo, AP1000(R) SBLOCA simulations with TRACE code, Ann. Nucl. Energy 75 (2015) 87-100. https://doi.org/10.1016/j.anucene.2014.07.045
  12. S. Kim, B.U. Bae, Y.J. Cho, Y.S. Park, K.H. Kang, B.J. Yun, An experimental study on the validation of cooling capability for the Passive Auxiliary Feedwater System (PAFS) condensation heat exchanger, Nucl. Eng. Des. 260 (2013) 54-63. https://doi.org/10.1016/j.nucengdes.2013.03.016
  13. N.R.C. Job, W. Code, RELAP5/MOD3 Code Manual (Validation of Numerical Techniques in RELAP5/MOD3), 1995.

피인용 문헌

  1. Indefinite sustainability of passive residual heat removal system of small modular reactor using dry air cooling tower vol.52, pp.5, 2020, https://doi.org/10.1016/j.net.2019.11.003
  2. Experimental study on transient thermal-hydraulic characteristics of an open natural circulation for the passive containment cooling system vol.179, 2019, https://doi.org/10.1016/j.ijheatmasstransfer.2021.121680