• DocumentCode
    3314729
  • Title

    Insights of level-2 PSA to prevent and mitigate severe accidents in IPHWR

  • Author

    Hari, Vibha ; Guptan, Rajee ; Dhame, S.P. ; Ghadge, S.G.

  • Author_Institution
    Nucl. Power Corp. of India Ltd., Mumbai, India
  • fYear
    2010
  • fDate
    14-16 Dec. 2010
  • Firstpage
    615
  • Lastpage
    618
  • Abstract
    Probabilistic safety assessment (PSA) uses a systematic approach to estimate the reliability and risk of a nuclear power plant (NPP). The level-2 PSA provides a structured assessment of the possible accident sequences that could occur following core damage and gives insights into which of the phenomena that could arise have the greatest potential to lead to containment failure or bypass resulting in a release of radioactive material to the environment. In some very low probability circumstances, severe accident sequences may result in core melting and plant damage leading to dispersal of radioactive material into the environment and thus constituting a health hazard to the public. The results of the level-2 PSA can be used to determine if sufficient provisions have been made to terminate core damage at an early stage and to prevent and mitigate the effects of the severe accident should the core damage progression continue. This gives insights into the level of robustness of the containment in providing protection for severe accidents and the adequacy of the accident management systems in protecting the containment and preventing a large release of radioactive material to the environment. PSA could find the plant vulnerabilities on severe accidents prevention and mitigation In addition, the level-2 PSAs are being used to identify any additional accident management measures that could be carried out to further mitigate the effects of a molten core. The paper discusses the relationship between Probabilistic Safety Assessment (PSA) and severe accident study and also introduce on how to apply PSA in severe accident prevention and mitigation. Some modifications or improvement as suggested based on level-2 PSA Study of KAPS 1&2 are presented in this paper.
  • Keywords
    fission reactor accidents; fission reactor containment; fission reactor safety; health hazards; heavy water reactors; nuclear power stations; IPHWR; NPP; accident management systems; accident sequence; containment failure; core damage; core damage progression; health hazard; level-2 PSA; mitigate severe accidents; molten core effect; nuclear power plant; plant damage; plant vulnerabilities; pressurized heavy water reactor; probabilistic safety assessment; radioactive material; severe accident sequence; severe accidents prevention; very low probability circumstances; Accidents; Guidelines; Instruments; Lead; Switches; Level 2 PSA; Severe Accidents Prevention and Mitigation;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Reliability, Safety and Hazard (ICRESH), 2010 2nd International Conference on
  • Conference_Location
    Mumbai
  • Print_ISBN
    978-1-4244-8344-0
  • Type

    conf

  • DOI
    10.1109/ICRESH.2010.5779623
  • Filename
    5779623