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CALCULATION OF RADIAL NEUTRON-FLUX DISTRIBUTION IN EGCR LATTICE CELL

Description: The neutron flux distributions in an EGCR cell containing seven and clusters of 2.0 and 2.6a enriched uranium odde were obtained by using a one- velocity, one-dimensional P-3 solution to the neutron transport equation and adjusting fluxes in the fuel cluster in a manner which is consistent with previous comparisons of experiments and calculated distributions. Flux traverses in the outer rod perpendicular to diameter of the cluster are also presented. (auth)
Date: August 31, 1959
Creator: DeBoer, T. K.
Partner: UNT Libraries Government Documents Department
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Decomposition of Nitrous Oxide Final Report. Period Covered: February 19, 1959-August 18, 1959

Description: The decomposition of N/sub 2/O in a reactor tube containing various fixed-bed catalysts was investigated at 200 to 700 deg C, space velocities of 250, 1250, and 2500 vol. of gas per vol. of catalyst per hr, and various gas mixture compositions. As catalysts, En at 500 deg C and Pd at 650 deg C both gave satisfactory results. NO/sub 2/ was formed with all these catalysts, the amount increasing as the residual N/sub 2/O decreased. (C.J.G.)
Date: August 31, 1959
Creator: Zufall, J. H. & Miller, H. S.
Partner: UNT Libraries Government Documents Department
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Dissolution of aluminium oxide as a regulating factor in aqueous aluminum corrosion

Description: The solubility of aluminum corrosion product in contact with metallic aluminum in deionized water has been determined over the range 80 to 350/sup 0/C. Evidence is presented to show that oxide dissolution results in the formation of a porous oxide on aluminum exposed in refreshed dynamic systems. Dynamic corrosion rate data have been analyzed on the basis of parabolic film growth and a linear oxide degradation process acting simultaneously on the system. The degradation process has been shown t… more
Date: August 31, 1959
Creator: Dillon, R.L.
Partner: UNT Libraries Government Documents Department
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New Production Reactor Thermal Shielded Studies

Description: The relative neutron capture gamma production in several prospective iron thermal shielding materials for the New Production Reactor was measured to determine the merit of adding boron to the metal. It was found that for the beam geometry the used addition of 1 1/2 percent boron to the iron before casting reduced the soft gamma production by a factor of 6.5 and the hard gamma production by a factor of 10. No attempt was made to measure gamma or neutron transmissions.
Date: August 31, 1959
Creator: Friesenhahn, S. J.
Partner: UNT Libraries Government Documents Department
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Pathfinder Atomic Power Plant Measurements of Nuclear Parameters of Boiler and Superheater Lattices

Description: Experiments are described which were designed to yield information pertinent to the evaluation of the nuclear parameters of various fuel-moderator lattices in the environment of the Sioux Falls Power Reactor (Controlled Recirculation Boiling Reactor) core. The test lattice section was enclosed in an element which replaced one of the fuel elements of the Penn State Reactor. Parameters measured were U/sup 236/ neutron capture cadmium ratio, space-averaged thermal neutron flux ratios, and reactivi… more
Date: August 31, 1959
Creator: Jacobs, A. & Vollmer, R.H.
Partner: UNT Libraries Government Documents Department
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Production test authorization IP-217-A-supplement, uranium sample irradiation (HAPO-218)

Description: The object of this production test is to authorize the irradiation of samples of natural uranium for use in the fission product volatilization program. Any empty central zone PCCF and/or process tube at B, D, DR, or H Reactors will meet the requirements of this authorization.
Date: August 31, 1959
Creator: Zima, G. E.
Partner: UNT Libraries Government Documents Department
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VARIABLE MODERATOR REACTOR DEVELOPMENT PROGRAM. Quarterly Progress Report No. 1

Description: Development of the boiling water UO/sub 2/ fueled Variable Moderator Reactor (VMR) is conducted under contract for the USAEC. The initiation and progress of work under Phase I of the contract, Physics and Kinetic Analysis and Initial Evaluation,'' and the preparation for Phase II, Critical Experiment and Analysis of Results,'' are reported. A hydrodynamic flow sheet representing the sequence of calculations for the BOCH program was prepared. A preliminary block diagram of the kinetics model of … more
Date: August 31, 1959
Partner: UNT Libraries Government Documents Department
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Construction Materials for Various Head-End Processes for the Aqueous Reprocessing of Spent Fuel Elements

Description: Materials of construction were evaluated for use in critical areas of head-end processes for the aqueous reprocessing of spent nuclear fuel elements. The SulfexThorex, Darex-Thorex, Darex, Zirflex, and Zircex processes were considered. The effect of varying heat treatments on the resistance of the materials was also evaluated. Dissolution of unirradiated fuel pins was carried out in vessels of promising materials. The corrosion rate of Ni-o-nel was about 5 mils per month during actual fuel-pin … more
Date: August 28, 1959
Creator: Peterson, C. L.; Miller, P. D.; Jackson, J. D. & Fink, F. W.
Partner: UNT Libraries Government Documents Department
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Design of production test IP-280-A-FP: Irradiation of alloyed dingot uranium fuel elements

Description: Objective of this test is to authorize irradiation of alloyed, low hydrogen dingot uranium fuel elements on a pilot scale, and to monitor their performance. Initially, 25 tons per month of alloyed, low hydrogen dingot material will be charged for two months. Measured charges will be loaded with the initial 25 tons to monitor the stability of this material. Following a two-month delay in the monitor charging, and if the dingot meets all specifications, routine charging of quantities up to 60 ton… more
Date: August 28, 1959
Creator: Hall, R. E. & Hodgson, W. H.
Partner: UNT Libraries Government Documents Department
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GAS-PRESSURE BONDING OF ZIRCALOY-CLAD FLAT-PLATE URANIUM DIOXIDE FUEL ELEMENTS

Description: A solid-state bonding technique involving the use of gas pressure at elevated temperatures was investigated for the preparation of compartmented Zircaloy-clad flat-plate uranium dioxide fuel elements. These investigations involved development of methods for the surface preparation and assembly of fuel- element components for bonding, determination of optimum bonding parameters, development of barrier coatings for uranium dioxide to prevent reaction with Zircaloy, and extensive testing and evalu… more
Date: August 28, 1959
Creator: Paprocki, Stan J.; Hodge, Edwin S.; Carmichael, Donald C. & Gripshover, Paul J.
Partner: UNT Libraries Government Documents Department
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OXIDE FLUORINATION TOWER

Description: A 3-inch-diameter flame tower for the conversion of uranosic oxide to uranium hexafluoride with elemental fluorine was tested for possible use in the fluorination step of the present uranium recovery process. The oxide was fed from a hopper to the tower by a screw feeder. The fluorine and the oxide entered at the top and flowed concurrently down through the tower. The unreacted or partially reacted oxide was collected in an ash receiver at the bottom. Fine solid particles were removed from the … more
Date: August 28, 1959
Creator: Peoples, L.C.
Partner: UNT Libraries Government Documents Department
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Design criteria -- Modification of fuel element test facilities. 1706-KER Project CGI-839

Description: The following criteria outlines the basis, objectives, and fundamental methods that shall govern the preparation of final design for ``Project CGI-839, Modification to Fuel Element Test Facilities -- 1706 KER.`` These modifications will provide the equipment to test NPR size fuel elements in the KER recirculating loops. The 1706-KER Recirculation Test Facility of KE Reactor is operated to obtain experimental data regarding high temperature reactor coolant technology and high temperature fuel el… more
Date: August 27, 1959
Creator: Rudock, E. R.
Partner: UNT Libraries Government Documents Department
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Fast Neutron Flux Measurements for Shielding Applications

Description: Pressed sulfur pellets, irradiated for two hours at 10 w yielded satisfactory counting rates on an internal proportional counter for measuring fast neutrons. The pellets were counted in their original form and an equation applicable to thick sources was applied to obtain disintegration rates. Decay data and beta energy analyses indicated that the induced activity was due to P/ sup 32/. Cross section values reported in the literature for the S/sup 32/(n,p)P/ sup 32/ reaction involved were found … more
Date: August 27, 1959
Creator: Roy, M.
Partner: UNT Libraries Government Documents Department
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P.T.: IP-272-A-FP, Pilot test of self-supported fuel elements in ribless zirconium process tubes

Description: Up to one hundred ribless zirconium process tubes are to be installed in C Reactor, and necessary reactor equipment modifications made to permit routine charging of these tubes with self-supported natural uranium fuel elements. This test authorizes continued loading in these tubes until authorized by process standards or until it is deemed impractical to convert C Reactor to this geometry.
Date: August 27, 1959
Creator: Hall, R. E. & Curtiss, D. H.
Partner: UNT Libraries Government Documents Department
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POWER REACTOR FUELS REPROCESSING. PROGRESS REPORT ON CORROSION STUDIES

Description: Work is reported on corrosion studies of candidate materials of construction for equipment for the dissolution of Zircaloy cladding in NH/sub 4/F- NH/sub 4/NO/sub 3/ solutions, the total dissolution of suainless steel clad fuels in HNO/sub 3/-HF solutions, and the dissolution of stainless steel cladding in dilute H/sub 2/SO/sub 4/. A single material of construction which could be used for a processing complex which would handle all of the low-enrichment fuels concerned was searched for. In the … more
Date: August 26, 1959
Creator: Maness, R.F.
Partner: UNT Libraries Government Documents Department
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Reprocessing of Are Fuel, Volatility Pilot Plant Runs E-3 Through E-6

Description: Reprocessing of the ARE fuel was resumed after extensive leak testing in the pilot plant. This was considered necessary to assure no recurrence of gaseous UF/sub 6/ leaks as experienced in Run E-2. In the four additional runs required to complete the program, about 641 kg of fluoride salt containing 40.64 kg of fully enriched uranium was reprocessed. Recovery as UF/sub 6/ product represented 97.97% of the feed, with 0.01% measured losses. An additional 2.14% was reclaimed from NaF beds. The pro… more
Date: August 26, 1959
Creator: Whitmarsh, C. L.
Partner: UNT Libraries Government Documents Department
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9-Zoom : A One-Dimensional, Multigroup, Neutron Diffusion Theory Reactor Code for the IBM 709

Description: The following document describes the usage and purpose of the neutron diffusion theory reactor program 9-Zoom, a memory-contained program that takes advantage of 709 features such as, for example, preferential order of multiply by zero, and for small problems approaches input-output limitations with excellent convergence properties.
Date: August 25, 1959
Creator: Stone, S. P.; Collins, E. T. & Lenihan, S. R.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Unit Operations Section Monthly Progress Report for May 1959

Description: The measured diffusivity of uranyl nitrate in water at 25 ction prod- C was 0.7 x 10/sup -6/ cm/sup 2//sec with about 40% average deviation. A program was started to develop nonnuclear uses for depleted uranium. Two continuous DRUHM reaction runs were terminated due to erratic operation of the sodium metering system. In the second Fluorox run with crude UF/sub 4/ which lasted for 29 hr, a total material balance of 94.8% was obtained and 17.9% of the theoretical amount of UF/sub 6/ was collected… more
Date: August 25, 1959
Creator: Bresee, J C; Haas, P A; Horton, R W; Watson, C D & Whatley, M E
Partner: UNT Libraries Government Documents Department
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THE DIFFUSION OF HYDROGEN IN BETA ZIRCONIUM

Description: Diffusion coefficients for hydrogen in beta zirconium were determined from permeation rates in the range 650 to 850 deg C. Both the steady-state method, which is dependent upon the hydrogen concentration, and the time-lag method, which is independent of hydrogen concentration, were employed to obtain diffusion data. Zirconium disks, 0.03 to 0.1 cm thick and varying in hydrogen concentration from 9 to 33 at.%, were used to measure permeation rates. The diffusion coefficients determined by the st… more
Date: August 25, 1959
Creator: Albrecht, William M. & Goode, W. Douglas, Jr.
Partner: UNT Libraries Government Documents Department
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Gamma Rays from Inelastic Scattering of 14-Mev Neutrons on Pb²⁰⁸

Description: Abstract: "The cross section for the production of 2.61-Mev gamma rays from the Pb-208(n, n')Pb-208* reaction has been measured for five different angles from 50 to 130 degrees. The angular distribution appears to be isotropic within the precision of the experiments, and leads to an integrated cross section of 25.5 +/- 4.6 millibarns."
Date: August 25, 1959
Creator: Hallett, Edward & Jensen, Roger
Partner: UNT Libraries Government Documents Department
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PROGRESS ON THE USE OF GAS-PRESSURE BONDING FOR FABRICATING LOW-COST CERAMIC, CERMET, AND DISPERSION FUELS

Description: Basic properties of several types and grades of commercial UO/sub 2/ have been determined. Compacting characteristics of these powders were evaluated with the objective of obtaining a minimum cold-pressed density of 70% of theoretical prior to gas-pressure bonding. Fused and special dense grades of UO/ sub 2/ powders were compacted to a density of 85% of theoretical by use of a 50- tsi compacting pressure. Cold-pressed compacts were simultaneously clad and densified to a maximum he UO/sub 2/ po… more
Date: August 25, 1959
Creator: Paprocki, S.J. ed.
Partner: UNT Libraries Government Documents Department
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A Separated 1.17-Bev/c K⁻ Meson Beam

Description: This report describes the design and testing of a 1.17-Bev/c separated K{sup -} beam designed in the fall of 1958 in connection with a 15-in. hydrogen bubble chamber experiment.
Date: August 25, 1959
Creator: Eberhard, Phillippe; Good, Myron L. & Ticho, Harold K., 1921-2020
Partner: UNT Libraries Government Documents Department
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Unit Operations Section Monthly Progress Report May 1959

Description: The measured diffusivity of uranyl nitrate in water at 25ºC was 0.7*10^e cm^2/sec with about 40% average deviation. A program was started to develop nonnuclear uses for depleted uranium. Two continuous DRUHM reaction tuns were terminate due to erratic operation of the sodium metering system. In the second Fluorox run with crude UF, which lasted for 29 hr, a total material balance of 94.8% was obtained and 17.9& of the theoretical amount of UF was collected in cold traps and chemical traps.
Date: August 25, 1959
Creator: Bresee, J. C.; Haas, P. A.; Horton, R. W.; Watson, C. D. & Whatley, M. E.
Partner: UNT Libraries Government Documents Department
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