Heat- and neutron-physical characteristics of power-generating units of nuclear power plants with VVER-1000 during operation above nominal power
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The margin to critical level of heat exchange of thermal power and coolant temperature at the core exit as well as the nonuniformities of the energy release under the operating conditions of a nuclear power plant with VVER-1000 above nominal power is analyzed for the No. 2 unit of the Balakovo nuclear power plant. It is confirmed that the safety criteria comply with OPB-88/97. The content of each of the three main stages of operation is presented. Conclusions are drawn and recommendations are made concerning updating the technical design of the reactor facility in order to increase the power level.
KeywordsEnergy Release Nuclear Power Plant Fuel Assembly Critical Heat Flux IRMS
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