Assessment of TRAC-PF1/MOD1 Code Against Condensation Induced Flow Oscillation at Cold Leg of PWRs During a Loss-of-Coolant Accident

  • Hajime Akimoto
  • Yoshio Murao
Conference paper

Abstract

TRAC-PF1 code is one of the most famous best-estimate code to analyze thermal-hydraulic behavior during postulated accidents in light water reactors.(1) During a loss-of-coolant accident of pressurized water reactors, a flow oscillation can be induced at cold leg due to direct contact condensation of flowing steam with injected subcooled water. Posttest calculations were performed to assess the predictive capability of the TRAC-PF1 code for the flow oscillation using data from a simulation test with scaled test facility.(2)

Keywords

Steam Liles 

Nomenclature

Cp

Specific heat of water

hfg

Latent heat of water for evaporation

mcmax

Condensability of injected water (=Cp(Tsat-Tli)mli/hfg)

mgi

Inlet steam mass velocity

mli

Inlet water mass velocity

Tli

Inlet water temperature

Tsat

Saturation temperature

X

Distance from water injection nozzle

References

  1. 1.
    Liles, D.,et al.; NUREG/CR-3858 LA-10157-MS (1986)Google Scholar
  2. 2.
    Akimoto, H.,et al.;J. Nuol. Sci. Technol. 22 (1985) 269–283.CrossRefGoogle Scholar

Copyright information

© Springer-Verlag Berlin Heidelberg 1988

Authors and Affiliations

  • Hajime Akimoto
    • 1
  • Yoshio Murao
    • 1
  1. 1.Reactor Safety Research Laboratory II, Tokai Research EstablishmentJapan Atomic Energy Research InstituteJapan

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