Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Investigation of a Hydrogen Mitigation System During Large Break Loss-Of-Coolant Accident for a Two-Loop Pressurized Water Reactor

  • Dehjourian, Mehdi (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) ;
  • Rahgoshay, Mohammad (Department of Nuclear Engineering, Science and Research Branch, Islamic Azad University of Tehran) ;
  • 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 : 2016.01.04
  • Accepted : 2016.04.05
  • Published : 2016.10.25
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Abstract

Hydrogen release during severe accidents poses a serious threat to containment integrity. Mitigating procedures are necessary to prevent global or local explosions, especially in large steel shell containments. The management of hydrogen safety and prevention of over-pressurization could be implemented through a hydrogen reduction system and spray system. During the course of the hypothetical large break loss-of-coolant accident in a nuclear power plant, hydrogen is generated by a reaction between steam and the fuel-cladding inside the reactor pressure vessel and also core concrete interaction after ejection of melt into the cavity. The MELCOR 1.8.6 was used to assess core degradation and containment behavior during the large break loss-of-coolant accident without the actuation of the safety injection system except for accumulators in Beznau nuclear power plant. Also, hydrogen distribution in containment and performance of hydrogen reduction system were investigated.

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References

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