Thermophysical properties of uranium-erbium fuel for VVER reactors

IF 0.3 4区 工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY
A. V. Fedotov, A. V. Lysikov, M. A Lutkov
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引用次数: 0

Abstract

The present study aims to determine the thermophysical properties of industrial uranium-erbium oxide pellets with an erbium content of 1.2 wt % to substantiate the performance and safety of fuel for VVER reactor plants. The performed study yields experimental dependences of thermal expansion, specific heat capacity at a constant pressure, thermal diffusivity, as well as the calculated dependence of thermal conductivity on the temperature up to 1900 K.

VVER反应堆用铀-铒燃料的热物理性质
本研究旨在确定含铒量为1.2 wt %的工业氧化铀-铒球团的热物理性质,以证实VVER反应堆工厂燃料的性能和安全性。所进行的研究得出了热膨胀、恒压比热容、热扩散率的实验依赖关系,以及热导率对温度高达1900 K的计算依赖关系。
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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来源期刊
Atomic Energy
Atomic Energy 工程技术-核科学技术
CiteScore
1.00
自引率
20.00%
发文量
100
审稿时长
4-8 weeks
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.
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