Calculation and experimental investigation of the heat removal modes of a shutdown BN-600 reactor of the beloyarsk nuclear power station

This paper examines the calculation and experimental investigation of heat removal modes from the core of a shutdown BN-600 reactor. The calculation was based on the thermal balance formula of the plant with ''dry'' steam generators of the third circuit. It is essential to know the speed of the heating up of the power plant in order to ensure its safe operation in case normal cooling of the core is disrupted. The circulation of the feed water was stopped before the experiments in which the speed of the heatup of the plant was determined. Calculations based on the experiments have shown that afterheat can be removed without a heat-up of the plant due to losses into the environment, without a supply of feed water into the steam generators. This is possible after the main circulators of two loops have been working for 25 days, or after those of one loop have been working for 45 days