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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ELECTROLYTIC DISSOLUTION OF NUCLEAR FUELS. PART III. STAINLESS STEEL (304) IN NITRATE SOLUTIONS

Description: The potential-current density relationships for 304 stainless steel dissolution in a nitrate system were studied as a function of solution composition and temperature in order to optimize the conditions for electrolytic dissolution of ihis material. In the nitrate system, the anodic dissolution of steel takes place in the transpassive region. Under some conditions, deviations from Tafel behavior are observed which depend greatly on the nitrate and hydrogen ion concentration, and on temperature.… more
Date: June 1, 1962
Creator: Aylward, J. R. & Whitener, E. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Bench-Scale Natural-Recirculation Dissolver

Description: A natural-recirculation dissolver closely approaching a stirred-tank reactor in behavior was developed, and its feasibility was demonstrated in the mercury-catalyzed dissolution of aluminum in nitric acid, It was designed to utilize the heat of reaction and evolution of gaseous reaction products for recirculation and mixing. The dissolvent was 5-molar nitric acid, containing mercury in concentrations from 10/sup -4/ to 10/sup -3/ molar as a catalyst. Dissolution rates for 1/7 scale, simulated M… more
Date: January 10, 1962
Creator: Erickson, E. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Chemical Development Section C Progress Report for October-December 1961

Description: Recovery of Th (and U) from Granitic Rock. Recovery of Th by acid leaching ten addltlonal granite samples (36 to 82 ppm Th) from the Conway formation in N. H. ranged from about 50 to 85%, and averaged about 70%, Study of the effect of grind size on the recovery of Th from Conway and Plkes Peak granites showed no significant differences in the range minus 20 to minus 200 mesh. The Th concentration in a sized Conway granite sample was found to be much greater in the fine than in the coarse fracti… more
Date: February 21, 1962
Creator: Brown, K.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Derivation of Equivalent Continuous Dilution for Cyclic, Unsteady Driving Forces

Description: This article uses an analytical approach to determine the dilution of an unsteadily-generated solute in an unsteady solvent stream, under cyclic temporal boundary conditions. The goal is to find a simplified way of showing equivalence of such a process to a reference case where equivalent dilution is defined as a weighted average concentration. This derivation has direct applications to the ventilation of indoor spaces where indoor air quality and energy consumption cannot in general be simulta… more
Date: December 15, 2010
Creator: Laboratory, Lawrence Berkeley National; Technical University of Denmark, Department of Civil Engineering; Mortensen, Dorthe K.; Walker, Iain S. & Sherman, Max H.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Rbu-Calculation of Reactor History Including the Details of Isotopic Concentration. Part 1. The Method

Description: RBU is a digital computer program for the detailed calculaticn of the neutron, reactivity, and isotopic history of a reactor in which relatively exact models of the geometry and physical processes are included to permit reliable predictions of fuel costs and reactor performance. The program uses the Monte Carlo method to obtain the fine structure of the neutron flux in three space dimensions and energy. Using this fine structure, cross sections are averaged over space and energy to obtain the n… more
Date: December 1, 1958
Creator: Leshan, E. J.; Burr, J. R.; Temme, M.; Morrison, R.; Thompson, G. T. & Triplett, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

HEALTH PHYSICS ASPECTS OF HANDLING URANIUM-233 FEED MATERIAL

Description: The processes of separation purification and fabrication of feed materials containing U/sup 232/, U/sup 233/, U/sup 234/, U/sup 23 and U/sup 238/ require much closer health physics supervision than do the enriched or naturally occurring mixtures of U/sup 234/, U/sup 235/, and U/sup 238/ found in natural uranium. The primary problem is the control of alpha and gamma radiation. The isotope U/sup 233/ presess only an alpha control problem; however, the daughters of U/sup 232/constitute a gamma pro… more
Date: October 31, 1958
Creator: Lawrence, J.N.P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Densities of Uranyl Sulfate Solutions Between 20° and 90°C

Description: The densiies of uranyl sulfate water solutions were measure or 12 concentrations between the temperatures of 20° and 90°C. The density range at 20°C is 1.0539 grams per cubic centimeter at 0.17 molal to 2.0059 grams per cubic centimeter at 3.9 molal.
Date: October 10, 1952
Creator: Jegart, J.S.; Heiks, J.R. & Orban, E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

THORIUM OXIDE SLURRY FILTRATION: PRELIMINARY TESTS OF A 3-MICRON POROLOY SINTERED FILTER RUNS 11, 12 AND 13 IN LOOP L-4-24S

Description: A Poroloy sintered-metal filter unit which was placed in a bpass arrangement in a 5-gpm loop, L-4-24S, for runs 11 and 12 was used to separate water from a flowing stream of thoria slurry. During runs ll and l2, the filter unit prevented the accumulation of thoria in the horizontal pressurizer during 490 hr of operation at temperatures up to 250 deg C and circulating stream concentrations up to 490 g Th/kg H/sub 2/0. Run 13 was made with the main stream of the loop flowing through the center of… more
Date: January 1, 1959
Creator: Jones, D.T. & Baker, J.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PRESSURE DROP EXPERIMENTS OF THE TITLE II FUEL ASSEMBLY FOR THE EXPERIMENTAL GAS COOLED REACTOR. SECTION III OF THE FUEL ASSEMBLY HEAT TRANSFER AND CHANNEL PRESSURE DROP EXPERIMENTS FOR THE EGCR RESEARCH AND DEVELOPMENT PROGRAM

Description: Data are presented on the pressure drop tests of the Title II fuel assembly design modification and refinements as occurred during the Title II test phase. All tests were conducted with the chosen 3.000-in. ID fuel assembly sleeve and with the outer six tubes of the seven-tabe cluster located on a 2.000- in. dia bolt circle. The tests included two designs of spider support pieces and three designs of midlength spacers. The pressure loss data are presented in the form of velocity head coefficien… more
Date: October 1, 1960
Creator: Crandall, W.H. & Higgins, R.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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