Nuclear Fuel Research: Fuel Cycle Development Program (Quarterly Progress Report: October 1 to December 31, 1959)
DOE
Key Details
- Posted Date
- Source
- doe_osti
Description
Work was continued on developing a process for the fabrication of uranium oxide fuel pellets by an inert atmosphere low-temperature sintering method. Oxidation rate and sintering studies for two oxides produced by Shattuck were completed. Using Davison and Spencer ADU oxides, an investigation of the effect of sintering cycle, mainly sintering temperature and soaking time, on sintered properties of non-stoichiometric UO<sub>2</sub> was undertaken. Results showed that it is possible to sinter nonstoichiometric UC<sub>2</sub> compacts to yield high densities and remove excess oxygen at the same time by sintering in nitrogen at 1300 C. Two methods of preparing UC were investigated. The powder consolidation approach involved the investigation of the reaction of uranium hydride with methane for preparation of the powder and cold pressing and sintering of the product. Arc melting of the component elements was the other method investigated. The optimum time and temperature were determined for the reaction of the methane with uranium hydride. Various compacting lubricants, compacting pressures, sintering times, and temperatures for the UC powder were investigated. Conditions were established for arc melting homogeneous 200 g UC buttons. Sound uniform bodies of UC 3/8" in diameter and 3/4" in length were produced by melting buttons in graphite molds. (For preceding period see NYO- 2684.). Authors: Holden, R. B. [Olin Mathieson Chemical Corp., New Haven, CT (United States). Metallurgical Labs.]; Hower, Jr., L. D. [Olin Mathieson Chemical Corp., New Haven, CT (United States). Metallurgical Labs.]; Fuhrman, N. [Olin Mathieson Chemical Corp., New Haven, CT (United States). Metallurgical Labs.]; Kalish, H. S. [Olin Mathieson Chemical Corp., New Haven, CT (United States). Metallurgical Labs.]; Bowman, F. E. [Olin Mathieson Chemical Corp., New Haven, CT (United States). Metallurgical Labs.]. Subjects: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; CHEMICAL REACTIONS-- COLD WORKING-- COMPACTING-- ELECTRIC ARCS-- LUBRICATION-- MELTING-- METHANE-- PELLETS-- POWDERS-- PREPARATION-- PRESSURE-- REACTION KINETICS-- SINTERING-- URANIUM CARBIDES-- URANIUM HYDRIDES; DENSITY-- ENVIRONMENT-- FABRICATION-- INERT GASES-- LOW TEMPERATURE-- NITROGEN-- OXIDATION-- OXYGEN-- PELLETS-- QUANTITY RATIO-- SINTERING-- TEMPERATURE-- URANIUM DIOXIDE; METALS, CERAMICS, AND MATERIALS
Frequently Asked Questions
Is this research still open?+
How do I apply for this research?+
Intelligence
- Win probability analysis
- Competitive landscape
- Incumbent analysis
- Price-to-win estimate
- Similar awards history
Data sourced from doe_osti