Assessing the Feasibility of an Accident Management Strategy Using Dynamic Reliability Methods

  • Moosung Jae (Hansung University Department of Industrial and Systems Engineering) ;
  • Kim, Jae-Hwan (Korea Atomic Energy Research Institute)
  • 발행 : 1997.02.01

초록

This paper presents a new dynamic approach for assessing feasibility associated with the implementation of accident management strategies by the operators. This approach includes the combined use of both the concept of reliability physics and a dynamic event tree generation scheme. The reliability physics is based on the concept of a comparison between two competing variables, i.e., the requirement and the achievement parameter, while the dynamic event tree generation scheme on the continuous generation of the possible event sequences at every branch point up to the desired solution. This approach is applied to a cavity flooding strategy in a reference plant, which is to supply water into the reactor cavity using emergency fire systems in the station blackout sequence. The MAAP code and Latin Hypercube sampling technique are used to determine the uncertainty of the requirement parameter. It has been demonstrated that this combined methodology may contribute to assessing the success likelihood of the operator actions required during accidents and therefore to developing the accident management procedures.

키워드

참고문헌

  1. Final Safety Analysis Report for Yonggwang Units 3&4 KEPCO
  2. The Study of IPEs of Nuclear Power Plants C.K. Park;n. 'Jae(et al.)
  3. NP-7071-CCML MAAP 3.0B Users Manual-Modular Accident Analysis Program for LWR Power Plants EPRI
  4. Reliability Engineering and System Safety v.22 Accident Sequence Dynamic Simulation versus Event Trees A. Amendola
  5. Reliability Technology A.E. GREEN;A.J. BOURNE
  6. Proceedings of International Conference, "New Trends in Nuclear System Themohydraulics" Quantification of Human Error Probabilities in Implementing Accident Management Strategies M. Jae;C.K. Park
  7. AiCHE Symposium Series, No.283 v.97 Steady-State Thermal Analysis of External Cooling of a PWR Vessel Lower Head H. Park;V.Dhir
  8. SNL, NUREG/CR-3624 v.1 A FORTRAN 77 Program and Users Guide for the Generation of Latin Hypercube and Random Samples for Use with Computer Models R.L. IMAN;M.J. SHORTENCARIER
  9. INEL, NUREG/CR-4639 v.1 Nuclear Computerized Library for Assessing Reactor Reliability(NUCLARR) D.I. Gertman(etc.)