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Effect of Spray System on Fission Product Distribution in Containment During a Severe Accident in a Two-Loop Pressurized Water Reactor

  • Dehjourian, Mehdi (Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University of Tehran) ;
  • Rahgoshay, Mohammad (Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University of Tehran) ;
  • Sayareh, Reza (Faculty of Electrical and Computer Engineering, Kerman Graduate University of Technology) ;
  • Jahanfarnia, Gholamreza (Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University of Tehran) ;
  • Shirani, Amir Saied (Faculty of Engineering, Shahid Beheshti University)
  • Received : 2015.11.18
  • Accepted : 2016.03.09
  • Published : 2016.08.25

Abstract

The containment response during the first 24 hours of a low-pressure severe accident scenario in a nuclear power plant with a two-loop Westinghouse-type pressurized water reactor was simulated with the CONTAIN 2.0 computer code. The accident considered in this study is a large-break loss-of-coolant accident, which is not successfully mitigated by the action of safety systems. The analysis includes pressure and temperature responses, as well as investigation into the influence of spray on the retention of fission products and the prevention of hydrogen combustion in the containment.

Keywords

References

  1. F.C. Rahim, M. Rahgoshay, S.K. Mousavian, A study of large break LOCA in the AP1000 reactor containment, Prog. Nucl. Energy 54 (2012) 132-137. https://doi.org/10.1016/j.pnucene.2011.07.004
  2. R. Frutos, D. Gido, G. Henneges, P. Schmuck, Calculation of fission product behaviour in an advanced containment in case of a severe accident, Nucl. Eng. Des. 202 (2000) 173-178. https://doi.org/10.1016/S0029-5493(00)00356-3
  3. CONTAIN 2.0 Code Manual, A Computer Code for Nuclear Containment Analysis, Prepared for the U.S. Nuclear Regulatory Commission, Patent, 1997.
  4. RELAP5/SCDAP//MOD3.2 Code Manuals, A Computer Code for Best-Estimate Transient Simulation of Light Water Reactor Coolant Systems During Severe Accidents, Prepared for the U.S. Nuclear Regulatory Commission, Idaho National Engineering and Enjvironmental Laboratory, NUREG/CR-6150, 1997.
  5. Nordostschweizerische Kraftwerke (NOK) AG, Beznau (KKB), Safety Analysis Report, 2003.
  6. B.R. Sehgal, Direct containment heating (DCH), in: Nuclear Safety in Light Water Reactors, first ed., Ch. 3, British Library Cataloguing in Publication Data, London, 2012, pp. 228-254.
  7. OECD, Status Report on Hydrogen and Related Computer Codes, Nuclear Energy Agency Committee on the Safety of Nuclear Installations, NEA/CSNI/R (2014)8, 2014.
  8. OECD, Documentation of the Use of Severe Accident Computer Codes in Selected Level-2 PSAs for Nuclear Power Plants, NEA/CSNI/R (97)19, Nuclear Energy Agency Committee on the Safety of Nuclear Installations, 1998.
  9. K. Mehboob, C. Xinrong, Source term evaluation of two-loop PWR under hypothetical severe accidents, Ann. Nucl. Energy 50 (2012) 271-284. https://doi.org/10.1016/j.anucene.2012.07.011

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