• DocumentCode
    3313448
  • Title

    Severe accident analysis to evolve insight for severe Accident Management Guidelines for Large Pressurised Heavy Water Reactor

  • Author

    Gokhale, Onkar ; Kumar, Mithilesh ; Gaikwad, A.J. ; Kumar, Rajesh ; Mukhopadhyay, D. ; Lele, H.G. ; Vaze, K.K.

  • Author_Institution
    Reactor Safety Div., Bhabha Atomic Res. Centre, Mumbai, India
  • fYear
    2010
  • fDate
    14-16 Dec. 2010
  • Firstpage
    276
  • Lastpage
    279
  • Abstract
    The Pressurised Heavy Water Reactor (PHWR) contains both inherent and engineered safety features that help the reactor become resistant to severe accident and its consequences. However in case of a low frequency severe accident, despite the safety features, procedural action should be in place to mitigate the accident progression. Usually for all these designs the Emergency Operating Procedures (EOPs) are developed in support of detailed accident analysis, which gives an adequate coverage for design basis accidents. Currently the designers are making provisions in design to mitigate progression of accidents arising from multiple failure accidents like Large Break Loss of Coolant Accident with failure of Emergency Core Cooling System and failure of moderator as heat sink. Many designs of Large PHWRs have adopted the approach of symptom based EOPs to handle multiple failure events as currently practiced for Light Water Reactors (LWRs). Severe accident analysis is an important aspect which complements Severe Accident Management Guidelines (SAMG) development process. These analysis provide insight into the accident progression and basis to develop the SAMG. The order of uncertainty in modelling the phenomena is very high. Hence it is emphasized that different computational models be used so that an un-biased “insight” can be evolved which can be used for SAMG development. The paper discusses two categories of severe accident analyses for such large reactors for multiple failure transients involving a high pressure scenario (initiation event like SBO) and low pressure scenario (initiating event like LOCA). The insight evolved from these analysis is being discussed in the paper.
  • Keywords
    fission reactor accidents; fission reactor cooling; fission reactor core control; heavy water reactors; light water reactors; LOCA; SAMG; accident progression; emergency core cooling system; emergency operating procedures; engineered safety; large break loss-of-coolant accident; light water reactors; pressurised heavy water reactor; severe accident analysis; severe accident management guidelines; Electron tubes; Guidelines; Heating; Channel uncovery; Ex - Core Loss of Coolant Accident; Moderator Boil off; Severe Accident Management Guidelines; Station Black Out;
  • 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.2010.5779560
  • Filename
    5779560