Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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STEAM GENERATOR TUBE INTEGRITY ANALYSIS OF A TOTAL LOSS OF ALL HEAT SINKS ACCIDENT FOR WOLSONG NPP UNIT 1

  • Lim, Heok-Soon (Korea Hydro & Nuclear Power Co., Ltd., Central Research Institute) ;
  • Song, Tae-Young (Korea Hydro & Nuclear Power Co., Ltd., Central Research Institute) ;
  • Chi, Moon-Goo (Korea Hydro & Nuclear Power Co., Ltd., Central Research Institute) ;
  • Kim, Seoung-Rae (Nuclear Engineering Service & Solution)
  • Received : 2013.03.04
  • Accepted : 2013.09.06
  • Published : 2014.02.25
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Abstract

A total loss of all heat sinks is considered a severe accident with a low probability of occurrence. Following a total loss of all heat sinks, the degasser/condenser relief valves (DCRV) become the sole means available for the depressurization of the primary heat transport system. If a nuclear power plant has a total loss of heat sinks accident, high-temperature steam and differential pressure between the primary heat transport system (PHTS) and the steam generator (SG) secondary side can cause a SG tube creep rupture. To protect the PHTS during a total loss of all heat sinks accident, a sufficient depressurization capability of the degasser/condenser relief valve and the SG tube integrity is very important. Therefore, an accurate estimation of the discharge through these valves is necessary to assess the impact of the PHTS overprotection and the SG tube integrity of the primary circuit. This paper describes the analysis of DCRV discharge capacity and the SG tube integrity under a total loss of all heat sink using the CATHENA code. It was found that the DCRV's discharge capacity is enough to protect the overpressure in the PHTS, and the SG tube integrity is maintained in a total loss of all heat accident.

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References

  1. T.G. Beuthe and B.N. Hanna, Editor, "CATHENA MOD-3.5d/Rev 2 Input Reference", AECL-WL Report: 153-112020-UM-001, Revision 0, 2005 August, and T.G. Beuthe and B.N. Hanna, Editor, "CATHENA MOD-3.5d/Rev 2 GENHTP Input Reference", AECL-WL Report: 153- 112020-UM-002, Revision 0, 2005 August.
  2. Design Manual for Wolsong-1 NPP, "Design Manual-59-33300/63330", and page A-1-1, 44.
  3. Analysis Report for Wolsong NPP2, 3,4 NPP, "86-33300-AR-002, Revision 1", page I-1.
  4. Design Manual for Wolsong-2, 3&4, "86-33300/63330-DM-001", page A-64.
  5. FSAR Chapter 15, WSNPP-1, 2013.
  6. R, Oris, "Sustained Loss of All Heat Sinks Events in CANDU", CANDU Energy Presentation Material, Mar 2012.
  7. Chiheb Hasnaoui, "Development of a Discharge Model for the Bopp & Reuther Degasser/Condenser Relief Valves for Heat Sink Assessment", CNS Sixth International Conference on Simulation Methods in Nuclear Engineering, Montreal, Quebec, Canada, Oct 2004.
  8. Saurin Majumdar, Predictions of Structural Integrity of Steam Generator Tubes under Normal Operating, Accident, and Severe Accident Condition. Argonne National Lab., Sept. 1996.
  9. William D. Callister, Jr., "Fundamentals of Materials Science and Engineering".
  10. Reg. Guide 1.121, 2. Minimum Acceptable Wall Thickness, (4).