Modernized loss-of-coolant & blackout accident management strategy at nuclear power plants with wwer
DOI:
https://doi.org/10.15276/opu.1.60.2020.06Keywords:
accident management, loss of coolant, blackoutAbstract
The analysis of the known results of RELAP5/V.3.2 simulation for loss of coolant & blackout accidents at WWER nuclear power plants showed that the design accident management strategies with design passive safety systems do not provide the necessary safety conditions for the maximum permissible temperature of fuel claddings, the minimum permissible level of coolant in the reactor and feed water in the steam generators. This work presents the modernized loss of coolant & blackout accident management strategy based on promising heat removal passive systems, reactor level control systems and steam generator feed water level control systems. A conservative thermohydrodynamic model was developed to substantiate the modernized loss of coolant & blackout accident management strategy. The main conservative assumptions of the model: a complete long-term failure (for 72 hours) of all electric pumps of the safety systems is accepted and the maximum interloop leak (equivalent to the steam generator collector cover lift-up) is modelled. The analysis of the calculation results showed that the modernized loss of coolant & blackout accident management strategy provides the necessary safety conditions for the maximum allowable temperature of the fuel claddings, for the minimum acceptable level of coolant and feed water. The presented results of computational modelling of blackout accident management strategies for nuclear power plants can be used to modernize and improve symptom-informed emergency instructions and guidelines for the severe accident management at nuclear power plants with WWER. Application of the results of computational modelling of blackout accident management strategies is generally not substantiated for other types of reactor facilities. In this case, it is necessary to develop calculated models for blackout accident management taking into account the specifics of the structural and technical characteristics and operating conditions for safety related systems of nuclear power plants.
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