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- Title
Results of Investigations of BREST-Type Reactor Fuel Rods with Mixed Uranium-Plutonium Nitride Fuel, Irradiated in BOR-60 and BN-600.
- Authors
Grachev, A. F.; Zherebtsov, A. A.; Zabud'ko, L. M.; Zvir, E. A.; Kryukov, F. N.; Nikitin, O. N.; Skupov, M. V.; Ivanov, Yu. A.; Porollo, S. I.
- Abstract
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.
- Subjects
NUCLEAR fuel claddings; NUCLEAR fuel rods; FAST reactors; FUEL; NITRIDES; NUCLEAR fuels
- Publication
Atomic Energy, 2019, Vol 125, Issue 5, p314
- ISSN
1063-4258
- Publication type
Article
- DOI
10.1007/s10512-019-00487-4