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Chemical Technology Division Unit Operations Section Monthly Progress Report, September 1961

Description: Nine samples of ThO/sub 2/ -UO/sub 2/ prepared as part of the solgel process development studies showed no consistent effects from small variations in several process parameters. The reaction of methane and copper oxide was studied. Engineering studies of the continuous dissolution of simulated U-Zr-Sn fuels in 6.5 M NH4F, 0.6-1.0 M NH/sub 4/NO/sub 3/, 0.1 M H/sub 2/O/sub 2/ were continued in modified 6-in.-dia. equipment. A total of 1642 kg of U from NaK bonded SRE Core I fuel rods wad dejacke… more
Date: April 1, 1962
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Partner: UNT Libraries Government Documents Department
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SOLUBLE NEUTRON POISONS AS A PRIMARY CRITICALITY CONTROL IN SHIELDED AND CONTAINED RADIOCHEMICAL FACILITIES

Description: Studies indicated that the use of soluble poisons as a primary criticality control offers economic and other advantages in that it permits the factors of vessel size and shape and solution concentrations to be dictated by considerations other than those of criticality. It is believed that soluble poison criticality control can be made as reliable as other methods of coaditional control if the application is preceded by adequate development work and is monitored by multiple. independent safeguar… more
Date: July 26, 1962
Creator: Nichols, J.P.
Partner: UNT Libraries Government Documents Department
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Delayed Failure Hydrogen Embrittlement of Zirconium. Quarterly Report No. 2, December 15, 1961 to March 14, 1962

Description: The purpose of this investigation is to determine the extent to which Zr and Zr alloys exhibit delayed failure (static fatigune) as caused by a combination of absorbed H and applied stress. Both notched and unnotched specimens of unalloyed Zr and Zircaloy-2 were hydrogenated to 200 ppm and 500 ppm by means of a modified Sieverts apparatus; specimens were evaluated at room temperature. Thus far, no time-dependent fracture was observed which can be attributed to the delayed failure phenomenon; it… more
Date: March 30, 1962
Creator: Weinstein, D. & Holtz, F. C.
Partner: UNT Libraries Government Documents Department
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SALT PHASE CHLORINATION OF REACTOR FUELS. III. CATALYZED DISSOLUTION OF URANIUM DIOXIDE IN LEAD CHLORIDE-CHLORIDE SYSTEMS

Description: The rapid dissolution of uranium dioxide is described, wherein copper is added to molten lead chloride at 550 deg C. and chlorine is passed through the melt. The integral dissolution of zirconium-clad uranium dioxide fuels is also described. The dissolution rate of uranium dioxide is directly proportional to the concentration of cuprous chloride if an excess of chlorine is used; the value for the rate constant is approximately 100 mg (UO/sub 2/) cm/sup -2/ min/sup -1/ (CuCl molality). The urani… more
Date: February 1, 1962
Creator: Vander Wall, E. M.; Bauer, D. L. & Hahn, H. T.
Partner: UNT Libraries Government Documents Department
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HOT CELL DEMONSTRATION OF ZIRFLEX AND SULFEX PROCESSES. Report No. 3

Description: ABS>Hot cell demonstration of the Zirflex decladding process coupled with a modified Purex solvent extraction process was completed using specimens of Zircaloy-clad UO/sub 2/ irradiated to levels of 6150-14,600 Mwd/TU. Soluble losses of uranium and plutonium to the decladding solutions were about 0.05%. Centrifugation of the decladding solution is probably necessary to remove up to 1% of the UO/sub 2/ present as fines resulting from the fracture of low (93 to 95%) density pellets; high (96%) de… more
Date: May 14, 1962
Creator: Goode, J.H. & Baillie, M.G.
Partner: UNT Libraries Government Documents Department
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High-Temperature Reactions of Type 304 Stainless Steel in Low Concentrations of Carbon Dioxide and Carbon Monoxide

Description: Compatibility studies of type 304 stainless steel in helium containing low concentrations of CO and CO/sub 2/ were conducted. The oxidation rates were insensitive to impurity concentrations between 0.0006--0.3 vol% in the temperature range 400--1000 deg C when P/sub co2/P/sub co/ was less than 0.66. Ratios above this value resulted initially in a slow oxidation rate, but was followed by an accelerated attack. The incubation period for the break-away varied with the P/sub co2//P/sub co/ ratio an… more
Date: August 29, 1962
Creator: Inouye, H.
Partner: UNT Libraries Government Documents Department
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Chlorination of Uranium and Fission Product Oxides in Molten Halide Media

Description: The chlorination of mixtures of uranium and fission product oxides in various molten halide systems by sparging with a chlorine-carbon monoxide mixture was investigated. The chlorination reaction causes the suspended oxide to form species that are soluble in the molten salt and removes some of the fission product elements by volatilization of the chlorides. The rate ot oxide dissolution and the fission product behavior both proved to be dependent upon the composition of the molten halide medium… more
Date: May 1, 1962
Creator: LaPlante, J. P.; Wenz, D. A. & Steunenberg, R. K.
Partner: UNT Libraries Government Documents Department
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An Evaluation of the Uranium Contamination on the Surfaces of Alclad Uranium-Aluminum Alloy Research Reactor Fuel Plates

Description: Reported radioactivity in the Low-Intensity Test Reactor (LITR) water coolant traceable to uranium contamination on the surfaces of the alclad uranium-- aluminum plate-tyne fuel element led to an investigation to determine the sources of uranium contamination on the fuel plate surfaces. Two possible contributors to surface contamination are external sources such as rolling-mill equipment, the most obvious, and diffusion of uranium from the uranium-aluminum alloy fuel into the aluminum cladding.… more
Date: March 19, 1962
Creator: Beaver, R. J.; Erwin, J. H. & Mateer, R. S.
Partner: UNT Libraries Government Documents Department
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The Uranium-Rich End of the Uranium-Zirconium System. Final Report- Metallurgy Program 3.1.3.

Description: The uranium-rich end of the uranium-zirconium alloy system was reinvestigated. The solubilities of zirconium in alpha and beta uranium were found to be 0.21 wt% at 662 deg C and 0.41 wt% at 693 deg C, respectively. The monotectoid decomposition of gamma /sub 1/ at 693 deg C and the eutectoid decomposition of t 662 deg C were confirmed. For alloys containing less than 150 ppm of oxygen by weight, the gamma /sub 1/ plus gamma /sub 2/ phase region boundaries were located at 4.5 and 22.0 wt% zircon… more
Date: February 1, 1962
Creator: Zegler, S. T.
Partner: UNT Libraries Government Documents Department
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PROCESSING OF POWER REACTOR FUELS SIXTEENTH QUARTERLY PROGRESS REPORT, JULY 1 TO OCTOBER 1, 1961

Description: In the semiworks dissolver, average currents were about 2000 amp during dissolution of stainless steel and about 1200 amp during dissolution of Zircaloy. These currents were obtained when the current was transferred to a fuel assembly by direct contact with the columbium basket. High dissolution rates are anticipated when the dissolver is modified so that the electrolyte makes the only electrical contact with the charge. Laboratory experiments were made to determine the important characteristic… more
Date: February 1, 1962
Creator: Rust, F.G. comp.
Partner: UNT Libraries Government Documents Department
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Extraction of Niobium-95 From Nitric Acid Solutions With Tri-N-Butyl Phosphate

Description: The distribution coefficient (DC o/a) of Nb/sup 95/ between aqueous nitric acid and 30% Tri-n-butyl phosphate (TBP) in n-dodecane increased from ~0.004 to O.1 N acid deficient solution to 0.05 in 4 M HNO/sub 3/ for the extractable portion of the niobium. Greater than 70% of the niobium was unextractable. The presence of 3% chemically degraded TBP, 7% chemically degraded Amsco, or both decreased the amount of unextractable niobium to <20% and degraded TBP increased the distribution of the extrac… more
Date: July 1, 1962
Creator: Moore, J. G. & Rainey, R. H.
Partner: UNT Libraries Government Documents Department
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An Improved Aqueous Process for Zirconium Alloy Nuclear Reactor Fuels. Part I. Preliminary Laboratory Studies

Description: The expanding use of Zircaloy-clad Zr-enriched U alloy fuel suggested a need for higher capacity reprocessing facilities. The most ungent requirement is for continuous dissolution equpment to match the solvent extraction capacity already available at Idaho Chemical Processing Plant. Because of the rapid disaolution rates possible with aqueous HF on clean metal as well as on oxidized fuels, and subsequent flowsheet economics, it is the reagent of choice. Laboratory measurements and a survey of t… more
Date: October 30, 1962
Creator: Rohde, K. L.; Newby, B. J.; Paige, B. E.; Roeh, A .P,; Hoffman, T. L. & Decker, L. A.
Partner: UNT Libraries Government Documents Department
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SOME OBSERVATIONS REGARDING RARE-EARTH LACTATES

Description: Lactates of all the rare earths except lanthanum, cerium, and praseodymium were prepared and studied. In the case of lanthanum, cerium, and praseodymium the laciates are apparently so soluble that they cannot be crystallized directly from aqueous solution. Products obtained by addition of anhydrous ethanol to sirupy solutions of the iight-rare-earth lactates were not well characterized and were deliquescent. Neodymium lactate trinydrate was prepared only by the addition of alcohol to a sirupy s… more
Date: March 28, 1962
Creator: Powell, J.E. & Farrell, J.L.
Partner: UNT Libraries Government Documents Department
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vic-Dioximes as Analytical Reagents

Description: A review of research that has contributed to a better understanding of the solubility relations among vicdioximes is presented. Included are sections on synthesis, analysis, structure, and analytical uses of these complexes (J.R.D.)
Date: March 1, 1962
Creator: Banks, Charles V.
Partner: UNT Libraries Government Documents Department
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THORIUM-MOLYBDENUM PHASE DIAGRAM

Description: The phase diagram of the Th-- Mo alloy system has been determined to be of the eutectic type with a eutectoid reaction associated with the Th alpha-beta transformation. X-ray, thermal, electric resistance, and metallographic methods have established the eutectic point at 1380 plus or minus 10 deg C and 7.0 plus or minus 0.5 wt% Mo. A eutectoid reaction is proposed at 1358 plus or minus 5 deg C and less than 0.1 wt% Mo. No solubility of Th in Mo was detected at 1325 deg C. (auth)
Date: March 27, 1962
Creator: McMasters, O.D.; Palmer, P.E. & Larsen, W.L.
Partner: UNT Libraries Government Documents Department
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The Use of Phosphite and Hypophosphite to Fix Ruthenium From High-Activity Wastes in Solid Media

Description: Fission product Ru, normally volatile to the extent of 20 to 60% in evaporation and calcination of simulated high level radioactive wastes at 500 to 1000 deg C, can be 99.9% retained in the solid product by addition of 2 moles of phosphite or hynophosphite per liter of waste. As little as 0.1 mole per liter lowered the Ru volatility during distillation approaching equilibrium by factors which varied from 38 for Darex to 225 for TBP-25 (aluminum) waste solutions. The final products with Purex, T… more
Date: June 19, 1962
Creator: Godbee, H. W. & Clark, W. E.
Partner: UNT Libraries Government Documents Department
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Stability Constants and Intrinsic Solubility of Several Nickel(II)-vic- Dioxime Complexes

Description: An investigation was made to determine the stability constants for several Ni(II) vic-dioximes and to calculate their intrinsic solubility constants. Data and discussion concerning dimethylglyoxime, diethylgiyoxime. di- npropylglyoxime, ethylmethylglyoxime, 4-isoproplynioxime, nioxime, 4- methylnioxime, 3-methylnioxime, heptoxime, and Ni(II) complexes of these vic- dioximes are presented. (J.R.D.)
Date: March 1, 1962
Creator: Banks, C. V. & Anderson, S.
Partner: UNT Libraries Government Documents Department
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A DIAPHRAGM PUMP FOR LIQUID METAL SERVICE

Description: The use of centrifugal and electromagnetic pumps for liquid metals is briefly reviewed. Details are provided on the construction and operation of a two-stage diaphragm pump successfully used for the first time in liquid metal service. From the results of a 5,376 hr test of the pump it was concluded that it is well suited to the pumping of liquid metals at low flow rates where pulsating flow can be tolerated. Operating temperatures and pressures are limited only by the availability of suitable m… more
Date: October 1, 1962
Creator: Westerheide, D.E.; Clifford, J.C. & Burnet, G.
Partner: UNT Libraries Government Documents Department
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HOT CELL DEMONSTRATION OF ZIRFLEX AND SULFEX PROCESSES. Report No. 2

Description: Twelve Zircaloy-2 clad UO/sub 2/ specimens, irradiated in the NRK to about 15,500 Mwd/t and decayed about 9 months, were declad and core dissolutions completed. The pellets were fractured brt were essentially intact (i.e. had not fallen apart) when declad. The U losses ramged from 0.03 to 0.09%, due to solubility of U(IV) in the Zinflex reagent, and the U losses from 0.01 to 0.04%. The core pellets were 99.5% dlssolved in 4 M HNO/sub 3/-0.1M Al(NO/sub 3/)/sub 3/ in 5 hr, which was slightly fast… more
Date: January 26, 1962
Creator: Goode, J.H. & Baillie, M.G.
Partner: UNT Libraries Government Documents Department
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Aqueous Processing of Thorium Fuels

Description: The status of aqueous processing methods for thorium fuels is summarized, with principal emphasis on the stainless steel-clad ThO/sub 2/UO/sub 2/ type. Data were obtained principally from laboratory-scale experiments with fully irradiated fuel samples and engineering-scale tests with unirradiated fuel. Stainless steel cladding was easily dissolved with 4 to 6M H/sub 2/SO/sub 4/ (Sulfex process) or 5M HNO/sub 3/-2M HCl (Darex process) in LCNA (Nionel type) or titanium equipment, respectively, in… more
Date: March 14, 1962
Creator: Blanco, R. E.; Ferris, L. M. & Ferguson, D. E.
Partner: UNT Libraries Government Documents Department
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