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With emphasis on safety, this study addresses for better design condition for the cooling system in a wet-type interim spent fuel storage facility, using a probabilistic safety assessment method. To incorporate the design renovation into the design phase, a simple approach is proposed. By taking the cooling system of a reference design, a fault tree analysis was performed to identify the weak point of the considered system, and then basic factors for design renovation were defined. A total of 21 design alternatives were selected through the combination of the basic factors. Finally, the optimum design alternative for the cooling system is derived by means of the cost and effect analysis based on the estimated cost, system reliability and assumed probabilistic safety criteria. With the assumption that the failure frequency of at-reactor spent fuel cooling system compiles with probabilistic safety criteria for the interim spent fuel cooling system, it was shown that the optimum alternative should have l00% cooling loop redundancy with one pump per cooling loop and a cleanup system installed separately from the main loop. Furthermore, it also should be classified into safety system. The result of this study can be used as a useful basis to identify factors of safety concern and to establish design requirements in the future. The method also can be applied for other nuclear facilities.

참고문헌 (10)

  1. Final Level Ⅰ PRA for YGN Unit 3-4, CE-NPSD-742 , KAERI , Document No. Z-018-CA-349-00, KAERI's Project Report / v.,pp., 1992
  2. M.S. Peters;K.D. Timmerhaus , Plant Design and Economics for Chemical Engineers / v.,pp., 1980
  3. Assessment of the Failure Rate and Unavailability of THORP Receipt and Storage Pond Water Cooling System , R.W. White , Doc. No. TRSPSWP/25, British Nuclear Fuel Plc., Risley / v.,pp., 1988
  4. Computer Code Package Development for Probabilistic Risk Assessment of Nuclear Power Plant , S.H. Chang(et al.) , KRC-85N-J05, Korea Electric Power Co. / v.,pp., 1987
  5. Optimization Techniques for System Reliability with Redundancy-A View , F.A. Tillman;C.L. Hwang;W.Kuo , IEEE Trans. on Reliability / v.R-26,pp.148, 1977
  6. Reactor Safety Study-An Assessment of Accident Risk in U.S. Commercial Nuclear Power Plants , U.S. Nuclear Regulatory Commission , WASH-1400, NUREG-75/014, U.S. Nuclear Regulatory Commission / v.,pp., 1975
  7. Storage Pool Cooling and Cleanup System in ISFSF Conceptual Design , SF-453-DIR-P001, KAERI's ISFSF Conceptual Design Report / v.,pp., 1990
  8. Regulatory Analysis for the Resolution of Generic Issue 82 , NUREG-1353, U.S. Nuclear Regulatory Commission / v.,pp., 1989
  9. The Construction of the Interim Spent Fuel Storage Facility , H.S. Park(et al.) , KAERI Ⅱ/PR-1/90, Korea Atomic Energy Research Institute / v.,pp., 1990
  10. Optimization Techniques for System Reliability: A Review , A.A. Mohamed;L.M. Leemis;A. Ravindram , Reliability Engineering and System Safety / v.,pp.137-14635, 1992

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