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A Discussion of the Metallurgical Aspects of Thorium as a Fuel Material

Description: Data on thorium are compiled and the use of thorium as a fuel material is discussed. It was assumed that the general reactor configuration will follow the conventional SGR-SRE reactor design of a graphite-moderated sodium-cooled metallic fuel system. Factors outlined which affect the use of thorium as a fuel material are availability of ore, capacity of processing plants, purity specifications, design and use of materials in fuel elements which may affect chemical separation economics, and technical feasibility. General metallurgical properties of thorium are described including melting point, density, chemical purity, thermal conductivity, thermal expansion, phase transformations, corrosion in liquid metals, tensile and creep strength, dimensional stability, and alloying properties. Methods of chemical processing, fabrication, and cladding are outlined. The advantages and disadvantages in the use of thorium as a fuel are summarized. (M.C.G.)
Date: November 1, 1953
Creator: Hayward, B. R.
Partner: UNT Libraries Government Documents Department

Preliminary Studies of Scavenging Systems Related to Radioactive Fallout. Letter Report No. 8 Covering Period June 1 to August 1, 1959

Description: Progress is reported on the separation of airborne particles into size fractions for radioactive analysis. Laboratory studies of scavenging systems were conducted using a latex suspension diluted 1 to 500 parts with polystyrene then atomized with a Lauterbach generator. Tests were conducted for the collection of polystyrene particles by an evaporating water droplet. The results from these tests are included. The size distributions of particles obtained from atomizing latex and 1% gelatin suspensions are tabulated. The latex suspensions were diluted 1:500, 1:100, and 1:10. Future laboratory studies are to be directed toward elimination of charged aerosol particles and the use of radiochemical techniques for determining the amount of material collected by a water droplet. (For preceding period see ARF-3127-7.) (B.O.G.)
Date: August 20, 1959
Creator: Stockham, J. & Rosinski, J.
Partner: UNT Libraries Government Documents Department

Collected Methods for Analysis of Sodium Metal

Description: Methods for analyzing chemical impurities in sodium metal samples are presented. Chemical analysis was used to determine impurities in calcium, carbon, chromium, iron, lithium, nickel, oxygen, potassium, and zirconium. Spectrographic analysis was used to determine other impurities. Sodium samples obtained from experimental apparatus were analyzed by these methods. (auth)
Date: October 15, 1959
Creator: Perrine, H. E.
Partner: UNT Libraries Government Documents Department

Chemical Methods for Routine Bioassay

Description: Methods in routine use for bioassay of materials of interest in U.S.A.E.C. biology programs are reviewed. Selected methods are given for Pu, Po, Ra, Th, T, U, and Sr. (T.R.H.)
Date: November 1, 1958
Creator: Hursh, J. B.
Partner: UNT Libraries Government Documents Department


Description: The recovery of urantum at the mine with portable equipment was shown to be feasible, using a process which involves grinding the ore, leaching with nitric acid, extracting with tributyl phosphate and kerosene, and precipitation with ammonia gas. The system is more expensive than a stationary plant but couid be used in an emergency or in difficulty accessible locations. The distribution of uranium was studied in various geographical locations and in several different materials including limestones, granites, clays, rivers and underground water, lignites, and volcanic ash and lavas. Geochemical studies, based on thermoluminescence, including stratigraphy, age determinations of limestones, and aragonite-calcite relations in calcium csrbonate are presented along with thermoluminescence studies of lithium fluoride, alkali halides, aluminum oxides, sulfates, and other inorganic salts and minerals. Radiation damage to lithium fluoride and metamixed minerals was studied, and apparatus was developed for measuring thermoluminescence of crystals exposed to gamma radiation, scintillameters for measuring alpha particle activity in materials containing a trace of uranium, and an analytical method for determining less than 1 part per million uranium. (J.R.D.)
Date: November 1, 1957
Creator: Daniels, F.
Partner: UNT Libraries Government Documents Department

Studies of the Behavior of the Tbp-Kerosene Solvent in Uranium Refining: Degradation of the Kerosene Diluent

Description: Extensive studies have been conducted of kerosenetype diluents for the tri-n-butyl phosphate (TBP)kerosene solvent used in uranium extraction. Wide variations have been shown in the paraffinic, isoparaffinics aromatics and olefinic hydrocarbon contents of these diluents. Such diluents have been shown to be unstable in thc presence of high nitric acid concentrations, and in the presence of small amounts of nitrous acid. This instability is primarily a function of the non-paraffinic hydrocarbon content of the diluent and of the nitrous acid concentration of the contacting medium. Degradation of a diluent has been shown to discolor a diluent, increase its density and viscositys and influence uranium distribution during re-extraction operations. Solvent treatment with Na/sub 2/CO/sub 3/, followed by H/sub 2/O and nitric acid washes, has been shown to be only partially effective in removing diluent degradation products. The diluent degradation products have been characterizeds chemically and spectrallys as carboxylic acids, organic nitrates, organic nitro compounds, and nitroso oompounds. (auth)
Date: August 12, 1958
Creator: Klopfenstein, R. K.
Partner: UNT Libraries Government Documents Department

Determination of Thorium in Uranium Ores and Feeds by Solvent Extraction Employing Thenoyltrifluoroacetone

Description: The thenoyltrifluoroacetone (TTA) extraction method has been investigated for the determination of microgram concentrations of thorium in uranium ores and concertrates. The tolerance limits for eighteen elements commonly found in uranium ore concentrates were established. The effect of phosphate on estraction of thorium was studied. Cobalt, copper, tin, and bismuth were found to seriously interfere with the Thoron method for the determination of thorium after a TTA extraction. A TTA extraction method is described for the separation of thorium and uranium from the interfering ions, employing preliminary acid sulfide and ammonium hydroxide separations. The method is rapid, and results obtained compare favorably with results obtained with other procedures. (auth)
Date: May 23, 1958
Creator: Laux, P. G. & Brown, E. A.
Partner: UNT Libraries Government Documents Department

Laboratory and Pilot Plant Evaluation of Dyno Uranium Concentrate

Description: The laboratory and pilot plant evaluation of Dyno concentrate is presented. This concentrate meets all FMPC impurity tolerance limits except thorium and chloride limits. The thorium limit can be met by the m-containing this material will necessitate blending of the material with a good quality low- chloride-containing concentrate in the National Lead Company of Ohio refinery process. Laboratory digestion and extraction tests indicate that this material should present no other problems in pulse colunn processing. A pilot plant pulse column test indicated that this material should present no operational problems in the National Lead Company of Ohio Refinery. (auth)
Date: October 31, 1958
Creator: Leist, N. R.; Hicks, C. T. & Nelli, J. R.
Partner: UNT Libraries Government Documents Department

Summary Technical Report for the Period January 1, 1956 to March 31, 1956

Description: Studies were continued on the laberatory evaluation of Canadian gravity concentrate, processing of Th-containing U concentrates, extraction of U in a HNO/ sub 3/--TBP--UNH system, corrosion rates of stainless steel in 70% HNO/sub 3/, denitration process, corrosion resistance of chrome-plated drum dryer to raffinate solutions, UO/sub 2/F/sub 2/ reduction process, process studies in the UO/sub 3/ to UF/sub 4/ process, effects of reduction temperature and degree of hydration on reactivity of UO/sub 2/ pellets, conversion of ammonium diuranate to UF/sub 4/, reduction of UF/sub 4/, melting and casting of Nb--U alloys, production of U washers, recovery of U from scrap material, and fabrication of Th electrodes. New processes, special problems, and wet chemical and spectrochemsical development were considered. (For preceding period see NLCO- 601.) (J.R.D.)
Date: April 16, 1956
Creator: Simmons, J. W.
Partner: UNT Libraries Government Documents Department