FIELD: primarily, in experimental test facilities and simulators for personnel of nuclear power plants. SUBSTANCE: method involves use of experimental section simulating thermal and hydraulic processes in reactor core. Section has at least one heater provided, as a rule, with several units incorporating provision for independent control of energy release both lengthwise and over its perimeter. Heater simulates structural member of reactor core. Energy release in heater units is controlled by means of computer operating in real-time mode and using data on temperature of coolant flowing over heater surface. Volume steam content and/or coolant density is measured in one or more sectional areas of experimental section. Data on steam content and/or coolant density obtained during measurements and results of calculation of core structural member temperatures are used in neutron-physics calculations of nuclear reactor kinetics. Output data of such calculations are capacities of internal heat sources used in solving heat conduction equations for simulated structural member of reactor core. Computer functions to compensate for difference in calculated values of heat fluxes on heater surfaces over which coolant flows and over surfaces of core structural member simulated by this heater. EFFECT: improved precision of process simulation. 5 cl
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Authors
Dates
1995-09-20—Published
1991-10-09—Filed