• DocumentCode
    3314545
  • Title

    Safety study and human factor assessment of end-shield draining event for 220MWe Indian PHWRs

  • Author

    Gautam, A.P. ; Krishnakumar, P. ; Hajela, S. ; Vijaya, A.K. ; Guptan, R.K. ; Malhotra, P.K. ; Dhame, S.P. ; Ghadge, S.G.

  • Author_Institution
    Nucl. Power Corp. India Ltd., Mumbai, India
  • fYear
    2010
  • fDate
    14-16 Dec. 2010
  • Firstpage
    583
  • Lastpage
    589
  • Abstract
    In Indian PHWRs (Pressurized Heavy Water Reactors), one of the major functions of the end-shield cooling system is to maintain temperature across the end-shield components uniform and thereby minimizing thermal stresses. Safety analysis considers draining of water from end-shield cooling system as one of the postulated event. In the PSA (Probabilistic Safety Analysis) Level-l study, failure to manually shut-down the reactor following this event was found to be one of the major contributors to Severe Core Damage. The deterministic and probabilistic studies as detailed in the paper, realistically evaluate contribution of the postulated event of end-shield draining in core damage and make a major input to Risk Informed Decision Making.
  • Keywords
    decision making; fission reactor cooling; fission reactor core control; fission reactor safety; heavy water reactors; probability; risk analysis; PHWR; core damage analysis; end-shield cooling system; end-shield draining event analysis; human factor assessment; pressurized heavy water reactor; probabilistic safety analysis; risk informed decision making system; safety assessment; thermal stress analysis; Fabrication; Frequency modulation; Manuals; Niobium; Temperature distribution; CDF; PHWR; PSA; draining; end-shield;
  • 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.2010.5779615
  • Filename
    5779615