82 Matching Results

Search Results

Advanced search parameters have been applied.


Description: Data on the properties, constitution, compatibility, radiation behavior, fabrication, preparation, storage, and handling of uranium, thorium, and plutonium carbides are reviewed. 187 references. (C.J.G.)
Date: May 31, 1960
Creator: Rough, F.A. & Chubb, W. eds.
Partner: UNT Libraries Government Documents Department


Description: A process that was developed for the preparation of particles of thorium- uranium dicarbide is described. Granulated particles composed of powdered UO/sub 2/, ThO/sub 2/, and carbon were suspended in a bed of graphite flour and heated to convert the oxides to dicarbides. The particles were then melted to densify and spheroidize them, the graphite flour keeping them separated so that they would not flow together. (auth)
Date: November 12, 1962
Creator: Goeddel, W. V. & Shoemaker, H. E.
Partner: UNT Libraries Government Documents Department

Radionuclide Inventories for DOE SNF Waste Stream and Uranium/Thorium Carbide Fuels

Description: The objective of this calculation is to generate radionuclide inventories for the Department of Energy (DOE) spent nuclear fuel (SNF) waste stream destined for disposal at the potential repository at Yucca Mountain. The scope of this calculation is limited to the calculation of two radionuclide inventories; one for all uranium/thorium carbide fuels in the waste stream and one for the entire waste stream. These inventories will provide input in future screening calculations to be performed by Performance Assessment to determine important radionuclides.
Date: March 28, 2000
Creator: Goluoglu, K.L.
Partner: UNT Libraries Government Documents Department


Description: Thorium and uranium carbide nuclear fuel particles were evaluated by metallographic and x-ray diffraction techniques. Techniques were developed to etch the polished surface of Th--U carbide to reveal the grain structure. In addition, techniques to determine particle density and coating thickness were developed. Comparison of the data indicates that the use of spherical particles allowed for more precise determination of the coating thickness, density, and strength of coatings. Strength of individual particles was about 700 to 1300 g per particle. A large scatter in crushing-strength values was observed when individual particles were crushed. Consequently, a relative crushingstrength test was developed for comparing coating strength: loads were applied to a column of particles in stepped increments, and broken coatings were detected by observing a weight gain in moist air from hydrolysis of the Th--U carbides. A correlation of relative crushing strength and coating thickness was obtained. The crystal structure of the C coatings was found to depend on the temperature of deposition in the range from 1400 to 2400 deg C; the twodimensional structure became more defined with increasing deposition temperatures. Subsequent annealing at 2400 deg C of the coatings deposited at 1400 deg C and at 2200 to 2400 deg C produced graphitization, whereas those deposited at 1800 to 2000 deg C retained their two-dimensional character. Macrostructure of the coatings as revealed by metallographic techniques showed a concentric shell-like structure in the 1400 deg C deposits and mottled or conical structure in the 1800 deg C deposits. Annealing to higher temperatures did not alter the general appearance of either macrostructure. (auth)
Date: April 26, 1962
Creator: Engle, G. B.; Luby, C. S. & Bokros, J. C.
Partner: UNT Libraries Government Documents Department

HTGR fuel performance in the Peach Bottom Reactor

Description: From conference on reactor operating experience; Myrtle Beach. South Carolina, USA (5 Aug 1973). The Peach Bottom Reactor has operated very reliably with the Core 2 loading since startup in July 1970. High temperature operation of test elements containing fuel for larger HTGR plants has been an important part of Peach Bottom operation. Details of the Core 2 and test element performance are presented. (14 references) (auth)
Date: July 1, 1973
Creator: Turner, R.F.; Burnette, R.D. & Scheffel, W.J.
Partner: UNT Libraries Government Documents Department

Thorium ceramics data manual. Volume II. Nitrides. Revised

Description: Physical, chemical, and mechanical properties of thorium nitrides, alone and in combination with other nitrides and other thorium compounds. are collected from the literature through January 1973 (51 references). The thorium-nitrogen phase equilibrium is reviewed. Although mechanical property data are still sparse, recent physical and chemical characterization of ThN has confirined its high metallic conductivity, furnished detaii on hydrolysis and oxidation, and expanded the knowledge of the (Th,U)N and Th(C,N) systems. (auth)
Date: October 1, 1973
Creator: Peterson, S. & Curtis, C.E.
Partner: UNT Libraries Government Documents Department

Aqueous Corrosion Rates for Waste Package Materials

Description: The purpose of this analysis, as directed by ''Technical Work Plan for: Regulatory Integration Modeling and Analysis of the Waste Form and Waste Package'' (BSC 2004 [DIRS 171583]), is to compile applicable corrosion data from the literature (journal articles, engineering documents, materials handbooks, or standards, and national laboratory reports), evaluate the quality of these data, and use these to perform statistical analyses and distributions for aqueous corrosion rates of waste package materials. The purpose of this report is not to describe the performance of engineered barriers for the TSPA-LA. Instead, the analysis provides simple statistics on aqueous corrosion rates of steels and alloys. These rates are limited by various aqueous parameters such as temperature (up to 100 C), water type (i.e., fresh versus saline), and pH. Corrosion data of materials at pH extremes (below 4 and above 9) are not included in this analysis, as materials commonly display different corrosion behaviors under these conditions. The exception is highly corrosion-resistant materials (Inconel Alloys) for which rate data from corrosion tests at a pH of approximately 3 were included. The waste package materials investigated are those from the long and short 5-DHLW waste packages, 2-MCO/2-DHLW waste package, and the 21-PWR commercial waste package. This analysis also contains rate data for some of the materials present inside the fuel canisters for the following fuel types: U-Mo (Fermi U-10%Mo), MOX (FFTF), Thorium Carbide and Th/U Carbide (Fort Saint Vrain [FSVR]), Th/U Oxide (Shippingport LWBR), U-metal (N Reactor), Intact U-Oxide (Shippingport PWR, Commercial), aluminum-based, and U-Zr-H (TRIGA). Analysis of corrosion rates for Alloy 22, spent nuclear fuel, defense high level waste (DHLW) glass, and Titanium Grade 7 can be found in other analysis or model reports.
Date: October 8, 2004
Creator: Arthur, S.
Partner: UNT Libraries Government Documents Department