Results of BOR-60 reactor tests and post-reactor studies of experimental fuel rods with mixed uranium-plutonium nitride fuel.

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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]
Copyright of Atomic Energy is the property of Springer Nature and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract. (Copyright applies to all Abstracts.)
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  Data: Results of BOR-60 reactor tests and post-reactor studies of experimental fuel rods with mixed uranium-plutonium nitride fuel.
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  Data: <searchLink fieldCode="JN" term="%22Atomic+Energy%22">Atomic Energy</searchLink>. Sep2025, Vol. 136 Issue 5, p253-258. 6p.
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  Data: <searchLink fieldCode="DE" term="%22Nuclear+fuel+rods%22">Nuclear fuel rods</searchLink><br /><searchLink fieldCode="DE" term="%22Physical+%26+theoretical+chemistry%22">Physical & theoretical chemistry</searchLink><br /><searchLink fieldCode="DE" term="%22Materials+testing%22">Materials testing</searchLink><br /><searchLink fieldCode="DE" term="%22Nitrides%22">Nitrides</searchLink><br /><searchLink fieldCode="DE" term="%22Fast+reactors%22">Fast reactors</searchLink>
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  Data: 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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  Data: <i>Copyright of Atomic Energy is the property of Springer Nature and its content may not be copied or emailed to multiple sites without the copyright holder's express written permission. Additionally, content may not be used with any artificial intelligence tools or machine learning technologies. However, users may print, download, or email articles for individual use. This abstract may be abridged. No warranty is given about the accuracy of the copy. Users should refer to the original published version of the material for the full abstract.</i> (Copyright applies to all Abstracts.)
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      – SubjectFull: Materials testing
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