Simulation of loop test conditions for the modified SM reactor fuel rods and test results in justification of their performance
Irradiation conditions were simulated to test pilot modified fuel rods of the SM reactor under middle (10MW/m2) and maximal (up to 15MW/m2) thermal load. Some postirradiation results are presented. A conclusion was made about the performance of the pilot SM fuel rods with the U content increased by 20%. A comparative analysis of both test conditions and material tests of the SM fuel rods was performed. The material tests results were used as a basis to propose and justify a phenomenological model of fuel rods swelling.