期刊文献+

A Methodology for Producing Uniform Distribution of UO2 in a Tungsten Matrix 被引量:2

A Methodology for Producing Uniform Distribution of UO2 in a Tungsten Matrix
下载PDF
导出
摘要 We report a method to produce a uniform mixture of uranium dioxide spherical particles in a tungsten matrix. This method involves mixing 0.5 weight percent of high density polyethylene binder with 60 volume percent uranium dioxide spheres and 40 volume percent tungsten powders. Initially, hafnium oxide spheres were used as a surrogate for uranium dioxide spheres. The HfO2/W/PE powders were thoroughly mixed in a Turbula, then mixed on a hot plate above the drop point of the binder. These powders were then densified using spark plasma sintering. Microstructure was evaluated using scanning electron microscopy, density was measured and hardness measurements were made. Initial carbon content of the powders were measured and carbon content of the sintered materials was measured. Subsequently, W/UO2/Binder powders were mixed using the same methodology to ensure the process could be used for this system. These powders were sintered using hot isostatic pressing and microstructures evaluated. The resultant microstructures contained uniform distribution of HfO2 and UO2 particles in the tungsten matrix with very low carbon content.
出处 《Journal of Physical Science and Application》 2015年第4期255-262,共8页 物理科学与应用(英文版)
关键词 Nuclear propulsion TUNGSTEN depleted uranium oxide hafnium oxide powder processing spark plasma sintering. 二氧化铀 均匀分布 基体 钨粉 生产 聚乙烯粉末 扫描电子显微镜 高密度聚乙烯
  • 相关文献

参考文献14

  • 1Koenig, D. R. 1986. "Experience Gained from the Space Nuclear Rocket Program (Rover)." LA-10062-R Los Alamos National Lab., Los Alamos, NM.
  • 2Stewart, M. E. and Schnitzler, B. G. 2012. "Thermal, Fluid and Structural Analysis of a CERMET Fuel Element." In Proceedings of the 48th AIAA Joint Propulsion Conference, Atlanta, Georgia. AIAA 2012-3959.
  • 3Saunders, N. T., Gluyas, R. E. and Watson, G. K. 1968. "Feasibility Study of a Tungsten Water-Moderated Nuclear Rocket, II Fueled Materials." NASA TM X-1421.
  • 4Argonne National Laboratory. 1968. "'Nuclear Rocket Program Terminal Report." ANL-7236, Argonne, IL.
  • 5Haertling, C. and Hanrahan, R. J. 2007. "Literature Review of Thermal and Radiation Performance Parameters for High-Temperature, Uranium Dioxide Fueled Cermet Materials." Journal of Nuclear Materials 366: 317-35.
  • 6Baker, R. J., Daniel, J. L., Lobsinger, W. J., Scott, R. J., Snojds, F. A. and Roake, E. A. 1966. Basic Behavior and Properties of W-UO2 CERMETS. s.l.: Pacific Northwest Laboratory, BNWL-394, NASA Lewis Research Center Report NASA-CR-54840.
  • 7De Souza, J. P., Atre, S. V., Suri, P. K., Thomas, J. and German, R. M. 2002. "Understanding Homogeneity of Powder-Polymer Mixtures-Effect of Mixing on Tungsten Powder Injection Molding Feedstock." In Proceedings of 57th Congresso Annual da ABM, Sao Paulo, Brazil.
  • 8Suri, P., Atre, S. V., Thomas, J. A., Sghaier, K. and German, R. M. 2000. "Homogeneity of Powder-Binder Mixtures: A Microstructural Model." Advances in Powder Metallurgy and Particulate Materials. Metal Powder Industries Federation 4: 35-43.
  • 9Gillespie, T. 1983. "The Effect of Aggregation and Particle Size Distribution on the Viscosity of Newtonian Suspensions." Journal of Colloidal and Interface Science 94 (1): 166-73.
  • 10Lewis, T. B. and Nielsen, L. E. 1968. "Viscosity of Dispersed and Agglomerates Suspensions of Spheres." Transactions of the Society of Rheology 12 (3): 421-43.

同被引文献5

引证文献2

二级引证文献3

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部