КОМПЬЮТЕРНОЕ МОДЕЛИРОВАНИЕ ТЕПЛОФИЗИЧЕСКИХ ПРОЦЕССОВ В ЯДЕРНОМ РЕАКТОРЕ ВВЭР-1000

Abstract

The priority use of water-water reactors in the nuclear power industry is due to their advantages. Water is ideally suited as a moderator and refrigerant, providing compactness, high power and simple reactor design. Water-water reactors have high resistance and self-regulation due to the negative temperature coefficient of reactivity. Their activity is caused by short-lived nuclides, which facilitates biological protection and access to equipment. Water effectively removes heat. However, there are also disadvantages: high neutron absorption by water, the requirement of uniform distribution of water, corrosion activity, expensive cleaning system and temperature limitation. An increase in unit power is possible due to the equalization of heat generation in the core. This requires an accurate thermohydraulic calculation.

 As a result of the study, a theoretical thermohydraulic calculation of heat transfer in the heat-generating set of the VVER-1000 reactor was obtained for the weighted average and maximum values of heat release in the heat-generating set. Computer simulation of heat transfer was also carried out for the distribution of moderately loaded energy in the heat-generating set. The results obtained were compared and analyzed. As a result of the calculation, the distribution graph and temperature field of the heat-releasing element of the coolant, fuel and reactor in the shell of the VVER-1000 heat-releasing kit were obtained.

Keywords: Water-water power reactor (VVER); fuel release kit; separation element; coolant