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REACTION OF NITROGEN WITH NIOBIUM

Description: Reaction rates of niobium with nitrogen were determined gravimetrically from 675. to 875 deg C with a recording microbalance and volumetrically from 1100 to 1600 deg C with a modified Sieverts apparatus. Diffusion coefficients and terminal solubilities were determined from 800 to 1600 deg C by the concentration- gradient technique. Tne reaction of nitrogen with niobium follows a parabolic rate law at 675 to 1600 deg C. The expression for the diffusion coefficient for nitrogen in niobium at 800 … more
Date: July 1, 1959
Creator: Albrecht, William M. & Goode, W. Douglas, Jr.
Partner: UNT Libraries Government Documents Department
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THE ECONOMICS AND HAZARD POTENTIAL OF WASTE DISPOSAL

Description: The two most important considerations in the disposal of radioactive wastes are safety and economy. All other steps in the waste disposal complex must be tuned to accomplish these two goals. In general, the hazardous waste in the nuclear power complex affect the cost of the nuclear power reactor fuel cycle, the general environment since disposal must exclude radioactivity from the environment for over 500 years, the costs and/or methods of waste treatment including fission product utilization, … more
Date: July 1, 1957
Creator: Arnold, E.D.
Partner: UNT Libraries Government Documents Department
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HRT Pressure Vessel Temperatures During Operation - An Evaluation Using Data From Run 16

Description: A study was made of the data taken during HRT Run 16, concerning the temperatures and thermal stresses in the pressure vessel. By making heat balances across the blast shield cooling coils, the pressure vessel cooling system was shown to be performing satisfactorily. Estimates of the thermal stress in the pressure vessel wall show values which range from 1800 psi it low power to 6800 psi at 5 Mw. The thermal stress does not appear to be excessive in this power range. The over-all heat generatio… more
Date: July 1, 1958
Creator: Aven, R. E.
Partner: UNT Libraries Government Documents Department
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A Continuous Fission Product Separation Process; I. Removal of the Rare Earths (Lanthanum Cerium, Praseodymium, and Neodymium) From a Typical Liquid Bismuth-Uranium Reactor Fuel by Contact with Fused LiCl-KCl Mixtures

Description: Technical report investigating the distribution of rare earth elements between a liquid bismuth-uranium solution and fused KCI-LiCi mixtures. Report warrants further research on the liquid bismuth-uranium-fused salt system due to the benefit of continuous fission removal processes.
Date: July 1, 1951
Creator: Bareis, D. W.
Partner: UNT Libraries Government Documents Department
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PRODUCTION OF HEAVY WATER SAVANNAH RIVER AND DANA PLANTS. Technical Manual

Description: A summary is presented of the basic technical iniormation that pertains to processes that are used at the Dana and Savannah River Plants for the production of heavy water. The manual is intended primarily for plant operating and technical personnel and was prepared to supplement and provide technical support for detailed operating procedures. Introductory sections contain some background information on the history, uses, available processes, and analytical procedures for heavy water. They also … more
Date: July 1, 1959
Creator: Bebbington, W.P.; Thayer, V.R. eds. & Proctor, J.F. comp.
Partner: UNT Libraries Government Documents Department
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THE REACTION OF HYDROGEN WITH ZIRCONIUM-1 AND -25 w/o URANIUM ALLOYS

Description: Hydrogen-absorption isotherms were measured over the range 535 to 835 C for zirconium--1 wt.% and--25 wt.% uranium alloys. X-ray-diffraction studies were made over approximately the same temperature range for the zirconium--1, -- 25, and --50 wt.% uranium alloys. In general, the alloys resenable the zirconium- hydrogen system, modified by the presence of uranium. With 1 wt.% uranium, the phase boundaries of the zirconium--hydrogen system are shifted to slightly lower hy-drogen contents. With 25… more
Date: July 1, 1959
Creator: Bigony, Harold E.; Doig, J. Robert, Jr. & Krause, Horatio H., Jr.
Partner: UNT Libraries Government Documents Department
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MAXIMUM MISSILE RANGES FROM CASED EXPLOSIVE CHARGES

Description: Curves are calculated and plotted to show maximum missile ranges from TNT changes cased with aluminum or steel of various thicknesses. The maxfmum initial missile velocity is assumed to be 10,000 fps. General trajectory formulas are derived from which the range may be calculated for any initial missile velocity, as determined from the ratio of the case weight to the explosive weight. (auth)
Date: July 1, 1958
Creator: Bishop, R.H.
Partner: UNT Libraries Government Documents Department
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Pilot-plant studies of mercury-catalyzed dissolving of aluminum-jacketed fuel elements

Description: The objective of the experimental studies reported herein was to demonstrate the laboratory-developed mercury-catalyzed dissolving procedure on a pilot-plant scale by conducting a series of test dissolutions of aluminum-jacketed, unirradiated uranium in the 150-gallon downdraft type semiworks dissolver in 321 Building. It was desired to establish: (1) the effect of the larger-scale operation on time cycle; (2) dissolution rates of aluminum and uranium, (3) controllability of the reactions, and … more
Date: July 1, 1954
Creator: Bradford, J. L. & Adler, K. L.
Partner: UNT Libraries Government Documents Department
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DISSOCIATION ENERGIES OF GASEOUS OXIDES

Description: Preliminary thermodynamic tabulations for gaseous oxides are presented. (J.R.D.)
Date: July 1, 1958
Creator: Brewer, L
Partner: UNT Libraries Government Documents Department
open access

DEVELOPMENT AND PROPERTIES OF URANIUM-BASE ALLOYS CORROSION RESISTANT IN HIGH TEMPERATURE WATER. PART III. CORROSION MECHANISM OF URANIUM-BASE ALLOYS IN HIGH TEMPERATURE WATER

Description: The factors affecting corrosion resistance both of bare and of clad uranium-base alloys are reviewed and a mechanism proposed for their corrosion behavior. For unclad gamma-phase uranium alloys exposed to a high temperature water corrodent, it is proposed that the corrosion rate is determined primarily by the oxidation of the alloy by water. This behavior is contrary to that of alpha uranium in which the corrosion rate is primarily determined by the formation and subsequent oxidation of a nonad… more
Date: July 1, 1956
Creator: Burkart, M.W. ed.
Partner: UNT Libraries Government Documents Department
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