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

Dunn F. E.; Wilson E. H.; Feldman E. E.; Sun K.; Wang C.; Hu L. -W.

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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

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

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The conversion of the Massachusetts Institute of Technology Reactor (MITR) from the use of highly-enriched uranium (HEU) fuel-plate assemblies to low-enriched uranium (LEU) by replacing the HEU fuel plates with specially designed General Atomics (GA) uranium zirconium hydride (UZrH) LEU fuel rods is evaluated. The margin to critical heat flux (CHF) in the core, which is cooled by light water at low pressure, is evaluated analytically for steady-state operation. A form of the Groeneveld CHF lookup table method is used and described in detail. A CHF ratio of 1.41 was found in the present analysis at 10MW with engineering hot channel factors included. Thus, the nominal reactor core power, and neutron flux performance, would need to be reduced by at least 25% in order to meet the regulatory requirement of a minimum CHF ratio of 2.0. (C) 2017 Published by Elsevier B.V.

机译：麻省理工学院反应堆（MITR）通过使用专门设计的通用原子（GA）铀代替HEU燃料板，从使用高浓铀（HEU）燃料板组件转换为低浓铀（LEU）评估了氢化锆（UZrH）LEU燃料棒。对于稳态操作，通过分析评估了芯中的临界热通量（CHF）的裕度，该临界通量由轻水在低压下冷却。使用并详细描述了Groeneveld CHF查找表方法的一种形式。在本分析中，在包括工程热通道因素的情况下，在10MW下的CHF比为1.41。因此，标称反应堆堆芯功率和中子通量性能至少需要降低25％，才能满足最低CHF比为2.0的法规要求。（C）2017由Elsevier B.V.发布

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来源
《Nuclear Engineering and Design》 |2017年第6期|15-21|共7页
作者
Dunn F. E.; Wilson E. H.; Feldman E. E.; Sun K.; Wang C.; Hu L. -W.;
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作者单位

Argonne Natl Lab, 9700 S Cass Ave, Argonne, IL 60439 USA;

Argonne Natl Lab, 9700 S Cass Ave, Argonne, IL 60439 USA;

Argonne Natl Lab, 9700 S Cass Ave, Argonne, IL 60439 USA;

MIT, Nucl Reactor Lab, 138 Albany St, Cambridge, MA 02139 USA;

MIT, Nucl Reactor Lab, 138 Albany St, Cambridge, MA 02139 USA;

MIT, Nucl Reactor Lab, 138 Albany St, Cambridge, MA 02139 USA;

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收录信息美国《科学引文索引》(SCI);美国《工程索引》(EI);美国《生物学医学文摘》(MEDLINE);
原文格式 PDF
正文语种 eng
中图分类
关键词
MITR; TRIGA; Low-enriched uranium; Reactor conversion;

机译：MITR;TRIGA;低浓铀;反应器转化;

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1. Evaluating the effectiveness of dilution of the recovered uranium with depleted uranium and low-enriched uranium to obtain fuel for VVER reactors [J] . A Yu Smirnov, G A Sulaberidze, A A Dudnikov, Journal of Physics: Conference Series . 2016,第1期

机译：评估回收铀用耗尽铀和低富集铀稀释的有效性，从而获得VVER反应器的燃料
2. Startup Test Plan and Predictions for Highly Enriched Uranium to Low-Enriched Uranium Fuel Conversion at the University of Missouri Research Reactor [J] . Wilson Cowherd, John Stillman, Leslie Foyto, Nuclear Technology . 2021,第10期

机译：在密苏里州大学研究反应堆中对高富集铀的启动测试计划和预测，在密苏里大学的铀燃料转换
3. Radiological Dose Assessment for the Ghana Research Reactor-1 at Shutdown Using Dispersion Model: Conversion from High-Enriched Uranium to Low-Enriched Uranium Fuel [J] . BIRIKORANG, Sylvester Attakorah, Abrefah, Environmental Research, Engineering and Management . 2018,第1期

机译：加纳研究堆1停机时使用弥散模型的放射性剂量评估：从高浓铀到低浓铀燃料的转换
4. MODERATOR CONFIGURATION OPTIONS FOR A LOW-ENRICHED URANIUM FUELED KILOWATT-CLASS SPACE NUCLEAR REACTOR [C] . Jeffrey C. King, Leonardo de Holanda Mencarini, Lamartine N. F. Guimaraes International Nuclear Atlantic Conference . 2018

机译：适用于低富含铀燃料千瓦级空间核反应堆的主持人配置选项
5. PART I: SEPARATION BY CATION EXCHANGE OF THORIUM, ZIRCONIUM, IRON AND URANIUM. PART II. ION EXCHANGE EQUILIBRIUM STUDIES FOR URANIUM(IV), THORIUM AND CADMIUM AND CHROMATOGRAMS FOR URANIUM(VI). [D] . SAMEDY, SAIF R. 1958

机译：第一部分：通过阳离子交换分离T，锆，铁和铀。第二部分铀，IV，镉的离子交换平衡研究以及铀（VI）的色谱图
6. Evaluating ion exchange resin efficiency and oxidative capacity for the separation of uranium(IV) and uranium(VI) [O] . Deborah L Stoliker, Nazila Kaviani, Douglas B Kent, 2013

机译：评估离子交换树脂对铀（IV）和铀（VI）分离的效率和氧化能力
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

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

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