RESULTS OF INVESTIGATIONS OF BREST-TYPE REACTOR FUEL RODS WITH MIXED URANIUM-PLUTONIUM NITRIDE FUEL, IRRADIATED IN BOR-60 AND BN-600

摘要

The complex program of computational and experimental validation of dense fuel for fast reactors in Project Breakthrough provides for testing of fuel rods with mixed uranium-plutonium nitride fuel in the BOR-60 and BN-600 reactors. The irradiation parameters and post-reactor studies of the fuel rods of a BREST reactor are presented. Testing of fuel rods in BOR-60 to maximum burnup 5% h.a. and damaging dose 74.8 dpa and in BN-600 to maximum burnup 4.5% h.a. and damaging dose 53 dpa did not result in depressurization of the rods. The results of post-reactor tests of irradiated fuel rods - swelling of fuel, gas release from the fuel, mechanical and corrosion properties of the cladding - are presented.