Features of the behavior of the dispersion fuel METMET under irradiation

L. A. Karpyuk, A. M. Savchenko, Y. Konovalov, G. A. Kulakov, S. Maranchak, S. A. Ershov, E. Maynikov, A. Kozlov, A. L. Izhutov, V. Shishin, A. A. Sheldyakov, V. Yakovlev
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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.
辐照下分散型燃料METMET的特性
本文研究了以锆合金为基体的铀钼合金颗粒构成的METMET燃料组合物在辐照下的行为。反应堆后的研究证实,在MIR反应堆中辐照的中试燃料元件在显著热负荷下的燃耗达到61 MW /kgU,性能令人满意。辐照条件下燃料结构稳定,燃料棒各组分之间具有良好的相容性。METMET燃料成分的燃料棒作为一种耐受性较强的燃料,在浮动核电机组和小容量核电站的反应堆中具有良好的应用前景。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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