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MELCOR/MACCS simulation of the TMI-2 severe accident and initial recovery phases, off-site fission product release and consequences
Authors:T Haste  J Birchley  E Cazzoli  J Vitazkova
Affiliation:aPaul Scherrer Institute, 5232 Villigen PSI, Switzerland;bCazzoli Consulting, Wiesenweg 14, 5415 Nussbaumen, Switzerland
Abstract:MELCOR has become the preferred code of the Swiss nuclear industry and of PSI for severe accident analysis, on account of its integrated systems-level approach and validation against experiments and more detailed codes, while MACCS is commonly used by safety authorities for independent assessment of off-site consequences, in particular health effects. The present work arises out of a programme to assess MELCOR independently using empirical data consistent with the recommendations of the OECD/CSNI validation matrix for core degradation codes. The MELCOR 1.8.5RD calculations are based on a model for phases 1 and 2 provided by the code developers but with a simplified thermal hydraulic noding in certain regions and the inclusion of a simple representation of the fission product release and transport pathways. The model has also been extended to simulate phases 3, 4, and the continuing initial period of core recovery and stabilisation. These calculations are a first attempt to demonstrate a MELCOR–MACCS capability to simulate the whole plant accident sequence beyond phase 4, including the containment response and off-site consequences arising from fission product release from the containment. Emphasis is placed on the overall accident evolution and whole plant response, rather than the detailed behaviour. Results are compared with observed and deduced data for the major accident signatures and rough estimates for exposure based on off-site monitoring. The results provide a good basis for the NPP analysis foreseen.
Keywords:CSNI  Committee for the Safety of Nuclear Installations  ENEA  Ente per le Nuovo Tecnologie  l’Energia e l’Ambiente  EDEWBODY  estimated dose equivalent whole body  NSAC  Nuclear Safety Analysis Centre  OECD  Organization for Economic Cooperation and Development  PORV  pilot operated relief valve  PSI  Paul Scherrer Institut  PWR  pressurized water reactor  RCP  reactor coolant pump  RPV  reactor pressure vessel  SNL  Sandia National Laboratories  TEDE  total estimated dose equivalent  TMI-2  Three Mile Island  Unit-2  USNRC  United States Nuclear Regulatory Commission
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