Thermohydraulic analysis of fuel assembly of the WWER-1000 reactors at reduced power

It is important to make a safety assessment of different hypothetical scenarios in actual nuclear power plants (NPPs). Some of the common scenarios analyzed are coolant primary tube rupture. In this paper, instantaneous coolant loss occurred at 75% and 50%. The event was simulated under abnormal conditions using the TRETON code, which is used to treat light water reactor (WWER) fuel assemblies. It is based on an algorithm to solve the heat transfer function at multiple levels and develop a porous body. In the study, the operating modes of the main circulation pump on an incomplete number of fuel rods provided acceptable levels of uneven flow and heating; The temperature of the coolant, cladding and fuel did not exceed the limits.