Tests of fuel elements with uranium-plutonium nitride fuel in an IGR pulsed reactor

IF 0.4 4区工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY

Atomic Energy Pub Date : 2024-04-04 DOI:10.1007/s10512-024-01055-1

A. V. Kaplienko, V. V. Lemekhov, Yu. S. Cherepnin, A. V. Moiseyev, A. P. Zhirnov, A. N. Ivanyuta, I. M. Rozhdestvenskiy, D. Yu. Loginov, Ye. R. Mezhina, A. L. Izhutov, Ye. A. Zvir, G. V. Shevlyakov, I. N. Volkova, Ye. G. Batyrbekov, V. V. Baklanov, A. G. Korovikov, A. N. Kotlyar, A. A. Miller, R. A. Irkimbekov, A. D. Vurim

引用次数: 0

Abstract

Fuel elements with mixed uranium-plutonium nitride fuel were tested in an IGR reactor to justify their application in a BREST-OD-300 reactor. The mid-radial enthalpy limit for the fresh mixed nitride fuel as experimentally determined during IGR launching with fast reactivity input amounted to 167 cal/g. The maximum temperature of 1000 °C and its maintenance for 100 s, comprising one of the design limits for the fuel cladding temperature, was experimentally confirmed. The main results of the performed experiments and post-irradiation studies are analyzed.

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在 IGR 脉冲反应堆中使用氮化铀钚燃料进行燃料元件试验

氮化铀钚混合燃料元件在 IGR 反应堆中进行了测试，以证明其在 BREST-OD-300 反应堆中的应用是合理的。在使用快反应输入的 IGR 发射过程中，通过实验确定了新的混合氮化燃料的中径向焓极限为 167 卡/克。实验确认了 1000 ℃ 的最高温度及其 100 秒的维持时间，这是燃料包层温度的设计极限之一。对已进行的实验和辐照后研究的主要结果进行了分析。

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 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.