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Feasibility of Long Term Feed and Bleed Operation For Total Loss of Feedwater Event

Kwon, Young-Min  
  • 초록

    The conventional Equipment Environment Qualification (EEQ) envelope is developed based on the containment responses during the design basis events. The Safety Depressurization System (SDS) design without In-containment Refueling Water Storage Tank (IRWST) adopted in the Ulchin 3&4 challenges the conventional EEQ envelope during long term Feed and Bleed (F&B) operation due to the direct discharge of high mass and energy into the containment. Therefore, it is necessary to confirm that the containment pressure and temperature history during the long term F&B operation does not violate the conventional EEQ envelope. However, this subject has never been quantitatively assessed before. To investigate the success path of long term F&B operation this paper analyzes the thermal hydraulic response of the containment and Reactor Coolant System (RCS) until the completion of depressurization and cooldown of RCS into Shutdown Cooling System (SCS) entry condition. It is found that the SCS entry condition can be reached within 6 hours without violating the EEQ curve by proper operation of SDS valves, High Pressure Safety Injection (HPSI) pumps and active Containment Heat Removal System (CHRS). The suggested strategy not only demonstrates the feasibility of long term F&B operation but also can be utilized in the preparation of Emergency Procedure Guidelines (EPGs)


  • 참고문헌 (11)

    1. Ulchin Units 3&4 Preliminary Safety Analysis Report / v.,pp.,
    2. Containment Thermodynamic Analysis, CENPD-140-A / v.,pp.,
    3. Realistic Small Break LOCA Evaluation Model, CEN-373-P / v.,pp.,
    4. W.R. Cramond(et. al.) , Shutdown Decay Heat Removal Analysis of a Combustion Engineering 2-Loop Pressurized Water Reactor, NUREG/CR-4710 / v.,pp.,
    5. A Comparative Simulation of Feed and Bleed Operation during the Total Loss of Feedwater Event by RELAP5/MOD3 and CEFLASH-4AS/REM Computer Codes , Young M. Kwon;Jin H. Song;Tae S. Ro , Journal of Nuclear Technology / v.112,pp.,
    6. CESSAR-DC / v.,pp.,
    7. Appendix 3, Technical Specifications, Ulchin 3&4 NSSS Supply Contract , PUB-P-91ED02 / v.,pp.,
    8. G.G. Loomis;J.J. Cozzuol , Decay Deat Removal Using Feed-and-Bleed for U.S. Pressurized Water Reator, NUREG/CR-5072 / v.,pp.,
    9. Analysis of Total Loss of Feedwater Event for the Determination of Safety Depressurization System Bleed Capacity , Young M. Kwon;Jin H. Song;Tae S. Ro , Journal of Korean Nuclear Society / v.27,pp.,
    10. Class 1E Classification, CENPD-255-A / v.,pp.,
    11. B.E. Boyack(et. al.) , Los Alamos PWR Decay-Heat Removal Studies Summary Results and Conclustions, NUREG/CR-4471 / v.,pp.,

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