Production of 28 mu m zirconium carbide kernels using the internal gelation process and microfluidics

Hunt R. D.; McMurray J. W.; Helmreich G. W.; Eckhart B. D.; McAlister A. L.; Nelson A. T.

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Production of 28 mu m zirconium carbide kernels using the internal gelation process and microfluidics

机译：使用内部凝胶化工艺和微流体生产280μm氧化锆核

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Studies using internal gelation and microfluidics have shown that the production of sintered spheres with diameters below 200 mu m is possible. The addition of carbon can be problematic because of slow flow rates (100 mu L/min) and long run times (4 h). However, a solution of dispersed carbon, Cabot's TPX-101, was successfully used with solutions of zirconyl nitrate, urea, and hexamethylenetetramine to make zirconium microspheres with carbon. A simple carbothermic reduction using a maximum temperature of 2073 K and ultrahigh purity argon produced zirconium carbide kernels with an average diameter of 28 mu m and a standard deviation of 2.3 mu m. (C) 2019 Elsevier B.V. All rights reserved.

机译：使用内凝胶和微流体的研究表明，具有直径低于200μm的烧结球的产生是可能的。由于慢速流速（100μl/ min）和长时间（4小时），添加碳的添加可能是有问题的。然而，分散的碳，Cabot的TPX-101的溶液成功地与硝酸锆，尿素和六亚甲基四胺的溶液一起使用，使锆微球与碳。使用2073 k和超高纯度氩产生的碳化锆粒的最高温度，平均直径为28μm，标准偏差为2.3μm的标准偏差，简单的碳水化合物减少。（c）2019 Elsevier B.v.保留所有权利。

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来源
《Journal of Nuclear Materials: Materials Aspects of Fission and Fusion》 |2020年第1期|共4页
作者
Hunt R. D.; McMurray J. W.; Helmreich G. W.; Eckhart B. D.; McAlister A. L.; Nelson A. T.;
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作者单位

Oak Ridge Natl Lab POB 2008 Oak Ridge TN 37831 USA;

Oak Ridge Natl Lab POB 2008 Oak Ridge TN 37831 USA;

Oak Ridge Natl Lab POB 2008 Oak Ridge TN 37831 USA;

Oak Ridge Natl Lab POB 2008 Oak Ridge TN 37831 USA;

Oak Ridge Natl Lab POB 2008 Oak Ridge TN 37831 USA;

Oak Ridge Natl Lab POB 2008 Oak Ridge TN 37831 USA;

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原文格式 PDF
正文语种 eng
中图分类原子能技术;
关键词
Zirconium carbide kernels; Internal gelation; Microfluidics;

机译：锆碳化锆核;内部凝胶化;微流体;

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1. Production of 28 mu m zirconium carbide kernels using the internal gelation process and microfluidics [J] . Hunt R. D., McMurray J. W., Helmreich G. W., Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2020,第1期

机译：使用内部凝胶化工艺和微流体生产280μm氧化锆核
2. Preparation of uranium fuel kernels with silicon carbide nanoparticles using the internal gelation process [J] . Hunt R.D., Silva G.W.C.M., Lindemer T.B., Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2012,第1a3期

机译：使用内部凝胶化工艺制备具有碳化硅纳米粒子的铀燃料核
3. The addition of silicon carbide to surrogate nuclear fuel kernels made by the internal gelation process [J] . R.D. Hunt, J.D. Hunn, J.F. Birdwell, Journal of Nuclear Materials: Materials Aspects of Fission and Fusion . 2010,第1a3期

机译：通过内部凝胶化工艺添加碳化硅来替代核燃料内核
4. THERMODYNAMIC CONSIDERATION OF THERMAL PLASMA PROCESS FOR ZIRCONIUM CARBIDE PRODUCTION FROM ZIRCON CONCENTRATES [C] . Zivota G. Kostic, Predrag Lj. Stefanovic, Pavle B. Pavlovic, European conference on thermal plasma processes . 2001

机译：从锆石浓缩物中渗透碳化锆生产热等离子体工艺的热力学考虑
5. Processing of zirconium boride-zirconium carbide-zirconium disilicide ceramic by reactive metal penetration. [D] . Maheswaraiah, Nischel B. 2010

机译：通过活性金属渗透处理硼化锆-碳化锆-二硅化锆陶瓷。
6. Internal Cylindrical Grinding Process of INCONEL® Alloy 600 Using Grinding Wheels with Sol–Gel Alumina and a Synthetic Organosilicon Polymer-Based Impregnate [O] . Wojciech Kapłonek, Krzysztof Nadolny, Krzysztof Rokosz, 2020

机译：INCONEL®600合金的内圆柱磨削工艺采用砂轮与溶胶-凝胶氧化铝和有机硅聚合物基浸渍胶合成
7. Control of Urania Crystallite Size by HMTA-Urea Reactions in the Internal Gelation Process for Preparing (U, Pu)O₂Fuel Kernels [O] . Collins, J.L. 2005

机译：用于制备（U，pu）O _{2 燃料核的内部凝胶化过程中HmTa-尿素反应控制铀微晶尺寸}
8. Control of Urania Crystallite Size by HMTA-Urea Reactions in the Internal Gelation Process for Preparing (U, Pu)O₂Fuel Kernels [R] . 2005

机译：用于制备（U，pu）O _{2 燃料核的内部凝胶化过程中HmTa-尿素反应控制铀微晶尺寸}

Production of 28 mu m zirconium carbide kernels using the internal gelation process and microfluidics

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