Bibliographic Details
| Title: |
Results of BOR-60 reactor tests and post-reactor studies of experimental fuel rods with mixed uranium-plutonium nitride fuel. |
| Authors: |
Kryukov, F. N.1 (AUTHOR), Belyaeva, A. V.1 (AUTHOR) avbelyaeva@niiar.ru, Nikitin, O. N.1 (AUTHOR), Grin, P. I.1 (AUTHOR), Zhemkov, I. Yu.1 (AUTHOR), Skupov, M. V.2 (AUTHOR), Tarasov, B. A.2 (AUTHOR), Zabudko, L. M.3 (AUTHOR) |
| Source: |
Atomic Energy. Sep2025, Vol. 136 Issue 5, p253-258. 6p. |
| Subjects: |
Nuclear fuel rods, Physical & theoretical chemistry, Materials testing, Nitrides, Fast reactors |
| Abstract: |
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. [ABSTRACT FROM AUTHOR] |
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| Database: |
Engineering Source |
