The uranium zirconium hydride research reactor and its applications in research and education

机译：氢化铀锆研究堆及其在研究和教育中的应用

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This paper are described briefly the performance, the configuration and the prospects of extensive applications in science and technology and education of the Uranium Zirconium Hydride research reactor in China.

机译：本文简要介绍了中国铀氢化锆研究堆在科学技术和教育中的性能，配置和广泛应用的前景。

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来源
《2001 Workshop on the Utilization of Research Reactors Nov 5-9, 2001 Beijing, China》|2001年|p.149-155|共7页
会议地点 Beijing(CN)
作者
Chen Wei; Wang Daohua; Jiang Xinbiao; A Jinyan; Yang Jun; Chen Da;
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作者单位

Northwest Institute of Nuclear Technology P.O.Box 69 Department 9 Xi'an 710024,P.R.China;

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会议组织
原文格式 PDF
正文语种 eng
中图分类原子能技术;
关键词
pulse reactor; uranium zirconium hydride; prompt negative temperature coefficient inherent safety; pulsing operation;

机译：脉冲反应器;氢化铀锆;负温度系数提示固有安全性;脉冲运行;

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专利

1. Evaluation of a uranium zirconium hydride fuel rod option for conversion of the MIT research reactor (MITR) from highly-enriched uranium to low-enriched uranium [J] . Dunn F. E., Wilson E. H., Feldman E. E., Nuclear Engineering and Design . 2017,第Juna期

机译：评估MIT研究反应堆（MITR）从高浓铀到低浓铀的铀氢化锆燃料棒选件
2. Improving the Neutronic Characteristics of a Boiling Water Reactor by Using Uranium Zirconium Hydride Fuel Instead of Uranium Dioxide Fuel [J] . Galahom Ahmed Abdelghafar Nuclear engineering and technology . 2016,第3期

机译：通过使用氢化铀锆代替二氧化铀燃料改善沸水反应堆的中子学特性
3. Improving the Neutronic Characteristics of a Boiling Water Reactor by Using Uranium Zirconium Hydride Fuel Instead of Uranium Dioxide Fuel [J] . Ahmed Abdelghafar Galahom Nuclear engineering and technology . 2016,第3期

机译：通过使用氢化铀锆代替二氧化铀燃料改善沸水反应堆的中子学特性
4. The uranium zirconium hydride research reactor and its applications in research and education [C] . Chen Wei, Wang Daohua, Jiang Xinbiao, Workshop on the utilization of research reactors . 2003

机译：铀硫锆研究反应堆及其在研究与教育中的应用
5. Determination of uranium hydride and zirconium hydride by neutron vibrational spectroscopy. [D] . Glagolenko, Irina Y. 2001

机译：中子振动光谱法测定氢化铀和氢化锆。
6. High-Temperature Thermodynamic Functions for Zirconium and Unsaturated Zirconium Hydrides [O] . Thomas B. Douglas 1963

机译：锆和不饱和锆氢化物的高温热力学函数
7. Evaluation of a uranium zirconium hydride fuel rod option for conversion of the MIT research reactor (MITR) from highly-enriched uranium to low-enriched uranium [O] . F.E. Dunn, E.H. Wilson, E.E. Feldman, 2017

机译：评价硫锆硫化物燃料棒选择，将MIT研究反应器（MIT）转化为高富富富铀硫酸至低富集的铀
8. Safety Evaluation Report on High-Uranium Content, Low-Enriched Uranium-Zirconium Hydride Fuels for TRIGA Reactors, Docket No. 50-163, GA Technologies, Inc [R] . Virgilio, M. J., Bevan, R. 1987

机译：用于TRIGa反应堆的高铀含量，低浓度铀 - 氢化锆燃料安全评估报告，案卷号50-163，Ga Technologies，Inc

The uranium zirconium hydride research reactor and its applications in research and education

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