V. I. Skalozubov1, V. A. Kondratiuk2, O. A. Dorozh3, V. I. Filatov2
1 Interagency Center for Fundamental Scientific Research in Energy and Ecology Sector of the NAS of Ukraine, Odesа Polytechnic National University and Ministry of Ecology and Natural Resources of Ukraine, 1, Shevchenko Ave., Odesa, 65044, Ukraine
2 National Technical University of Ukraine “Igor Sikorsky Kyiv Polytechnic Institute”, 37, Beresteiskyi Ave., Kyiv, 03056, Ukraine
3 Educational and Scientific Institute of Energy of the Odesа Polytechnic National University, 1, Shevchenko Ave., Odesa, 65044, Ukraine
DOI: doi.org/10.31717/2311-8253.23.1.1
Abstract
A deterministic method of analyzing conditions for ensuring the safe operation of VVER-1000 and AP1000 nuclear power plants has been developed. The method is based on the comparison of the provision of the required safety functions by critical (minimum permissible) configurations of safety systems for accident management. During the analysis, the composition and information on the technical characteristics of the safety systems of the VVER-1000/320 and AP1000 reactor installations, which are designed to ensure the safety functions of feeding and cooling the reactor/PG, were considered. On the basis of the developed method, the relative criteria and safety conditions (for example — the criterion of safety — the maximum temperature of the heating element shell; the condition of safety is not to exceed the maximum design limit of damage to the twelfth (the temperature of the twelfth shell is 1,200 °C) for nuclear power plants with VVER-1000 and АР1000 reactors in terms of safety functions for emergency fueling and cooling of the reactor core and steam generators are determined. Preliminary estimates of the relative criteria and conditions for ensuring nuclear safety during accident management of natural circulation circuits of passive safety systems AP1000 obtained taking into account data on their composition and technical characteristics, the table showed that the required height of natural circulation circuits of passive safety systems should be several hundred meters. Based on the established relative criteria and safety conditions, the need for additional modernization of the АР1000 safety systems to successfully ensure the safety functions of emergency coolant/feedwater supply and core and steam generator cooling is preliminarily determined.
Keywords: safety, method of qualification of nuclear power plants
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