F. N. Kryukov, A. V. Belyaeva, O. N. Nikitin, P. I. Grin, I. Yu. Zhemkov, M. V. Skupov, B. A. Tarasov, L. M. Zabudko
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Results of BOR-60 reactor tests and post-reactor studies of experimental fuel rods with mixed uranium-plutonium nitride fuel
In the course of the study, various designs of experimental fuel rods with mixed uranium-plutonium nitride fuel and claddings made of various materials were tested as part of the dismountable irradiation devices of the BOR-60 reactor. The experimental fuel rods represent the mock-ups of the BREST-OD-300 and BN-1200 reactor fuel rods, which differ from the real ones in their shorter length, smaller gas collector volume, and fuel column height. Reactor tests and post-reactor studies of 2020–2023 provided new data on the state of fuel, various types of fuel rod claddings, and fuel assembly design elements.
期刊介绍:
Atomic Energy publishes papers and review articles dealing with the latest developments in the peaceful uses of atomic energy. Topics include nuclear chemistry and physics, plasma physics, accelerator characteristics, reactor economics and engineering, applications of isotopes, and radiation monitoring and safety.