MODELING OF COOLANT FLOW IN THE FUEL ASSEMBLY OF THE REACTOR OF A FLOATING NUCLEAR POWER PLANT USING THE LOGOS CFD PROGRAM

摘要

Results of computer modeling of coolant flow in the fuel assembly of the reactor of a floating nuclear power plant using the LOGOS CFD programs have been given. The possibility of using the obtained results to improve models built into the engineering programs of thermohydraulic calculation of nuclear-reactor cores has been considered.