• DocumentCode
    1167526
  • Title

    Transient analysis following tripping of a primary circulating pump for 500-MWe PHWR power plant

  • Author

    Gaikwad, Avinash J. ; Kumar, Rajesh ; Vhora, S.F. ; Chakraborty, G. ; Raj, V. Venkat

  • Author_Institution
    Reactor Safety Div., Bhabha Atomic Res. Centre, Mumbai, India
  • Volume
    50
  • Issue
    2
  • fYear
    2003
  • fDate
    4/1/2003 12:00:00 AM
  • Firstpage
    288
  • Lastpage
    293
  • Abstract
    The 500-MWe Indian pressurized heavy water (PHWR) incorporates many new features as compared to the earlier 220-MWe PHWRs. To evaluate the new design features like primary heat transport (PHT) system configuration with two loops, four primary circulating pumps (PCPs) and four passes through core, addition of a pressurizer (surge tank) in the PHT system along with a feed/bleed system and their safety-related implications, simulation model development and transient analyses are necessary. To mitigate the swell and shrinkage in the PHT system and to avoid high/low PHT system pressure during transients, a 30 m3 pressurizer along with feed/bleed system is also included in the PHT pressure control system for the 500-MWe PHWR. At the same time, a reactor stepback is also actuated during the one PCP trip transient after tripping the corresponding (same side) PCP in the other loop. The corresponding PCP in the healthy loop is tripped to avoid unsymmetrical flow and pressure distribution in the two identical loops. A detailed transient analysis is required to study the individual contributions of various systems and provisions such as pressuriser, feed/bleed, and reactor step/set back in mitigating the consequences of the malfunction.
  • Keywords
    fission reactor cooling; fission reactor core control; fission reactor design; fission reactor safety; nuclear engineering computing; pipe flow; pumps; swelling; two-phase flow; 220 MW; 500 MW; Indian pressurized heavy water; PHWR power plant; core; feed-bleed system; pressure distribution; pressurizer; primary circulating pump; safety; shrinkage; simulation model; surge tank; swell; transient analysis; tripping; unsymmetrical flow; Coolants; Equations; Feeds; Heat pumps; Inductors; Mathematical model; Power generation; Pressure control; Surges; Transient analysis;
  • fLanguage
    English
  • Journal_Title
    Nuclear Science, IEEE Transactions on
  • Publisher
    ieee
  • ISSN
    0018-9499
  • Type

    jour

  • DOI
    10.1109/TNS.2003.809600
  • Filename
    1190047