Features of the behavior of the dispersion fuel METMET under irradiation
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Published:2022-11-01
Issue:3(111)
Volume:
Page:148-155
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ISSN:1994-6716
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Container-title:Voprosy Materialovedeniya
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language:
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Short-container-title:Vopr. materialoved.
Author:
Karpyuk L. A.1, Savchenko A. M.1, Konovalov Yu. V.1, Kulakov G. A.1, Maranchak S. V.1, Ershov S. A.1, Maynikov E. V.1, Kozlov A. V.1, Izhutov A. L.2, Shishin V. Y.2, Sheldyakov A. A.2, Yakovlev V. V.2
Affiliation:
1. A.A. Bochvar High Technology Scientific Research Institute for Inorganic Materials (VNIINM) 2. State Scientific Center “Scientific Research Institute of Atomic Reactors” (JSC “SSC RIAR”)
Abstract
The paper considers the behavior under irradiation of the METMET fuel composition, which consists of particles of uranium-molybdenum alloy in a matrix of zirconium alloys. Post-reactor investigations confirmed the satisfactory performance of pilot fuel elements irradiated in the MIR reactor to a burnup of 61 MW day/kgU under significant thermal loads. The structural stability of the fuel under irradiation, good compatibility of the fuel rod components with each other could be noted. Fuel rods with METMET fuel composition have good prospects for use in reactors of floating nuclear power units and low-capacity nuclear plants, as well as a tolerant fuel.
Publisher
FSUE CRISM Prometey
Subject
General Earth and Planetary Sciences,General Environmental Science
Reference5 articles.
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