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Re-Evaluation of Chemical Potential of Imperial Irrigation District Well No. 1

Description: The chemical potential of the brine from I.I.D. Well No. 1 was evaluated and reported in Rogers Engineering Coo, Inc. March 1962 Flow Test Report. This evaluation considered only the recovery of sodium chloride, as the prime salable product and alternately as the raw material for conversion to salable chlorine and caustic. Both cases showed low net revenue relative to the estimated capital investment required. The subsequent three month well flow test indicates continued production of a consist… more
Date: April 1, 1963
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Gravity fed water supply to reactor storage basins

Description: It is the purpose of this document to provide the scope of piping changes that are needed to supply gravity-fed water to the reactor storage basins on an unattended basis following complete reactor discharge of metal into these basins.
Date: April 1, 1963
Creator: Hedges, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The N-Reactor fuel testing program in the KER loops

Description: The KER loops are four pressurized water-cooled in-reactor testing loops in which fuel, coolant and corrosion tests are being conducted for the N Reactor program. Two of the loops, KER-3 and KER-4, are equipped with N-size Zr-2 process tubes and have sufficient pumping and heat dissipation capacity to permit testing of 14-element charges of N fuel. The other two loops, HER-1 and KER-2, are fitted with Zr-2 process tubes of 2.1 in. inner diameter (vs 2.7 in. for N). The small loops can be used t… more
Date: April 1, 1963
Creator: Evans, T. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production test IP-550-I: Routine monitoring for moderator oxidation rates

Description: The objectives of this production test are: 1. To authorize the outage time involved in installing and removing oxidation monitors for the reactors, and 2. To specifically define sample design, spacing of samples in the channels, and residence times to insure adequate routine monitoring of moderator oxidation rates. This production test is concerned with B, C, D, F, DR, F, and H reactors. Similar requirements have been specified in PITA IP-20-I for KE and KW reactors
Date: April 1, 1963
Creator: Baars, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Pressure Equalization by Fluid Exchange Between Parallel Flow Channels

Description: Hydraulic and deflection analyses of the unequal flow passages in the HFIR control region revealed excessive pressure differentials. A proposal to drill connecting holes between the flow passages initiated an experimental program for investigating the effectiveness crossflow on pressure equalization. Empirical constants for an analytical model and experimental design data on reduction of pressure differentials between channels were obtained. It was determined that crossflow between channels wou… more
Date: April 1, 1963
Creator: Chapman, T.G. & Stevens, P.N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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USE OF La$sup 140$ AS RADIO-TRACER IN (PRE-BUGGY) CHEMICAL EXPLOSIONS. PREPARATION AND DETERMINATION OF ITS REACTION WITH ENVIRONMENTAL MATERIALS

Description: The pre-Buggy experiment was designed to measure the fraction of vented radioactivity from a series of HE underground detonations containing radioactive sources. Capsules containing curie amounts of La/sup 140/ were sufficient to provide a radiotracing of the debris which resulted from the detonation. Particle size measurements of the debris indicated that La/sup 140/ was adsorbed on the surface of the soil particles. Some 96% of the activity was associated with sub-sieve particles representing… more
Date: April 1, 1963
Creator: Lane, W.B.; Nuckolls, M.J. & Railey, R.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HIGH-TEMPERATURE LIQUID-METAL TECHNOLOGY REVIEW. A Bimonthly Technical Progress Review. Volume 1, Number 2

Description: Metals ---technology of high-temperature liquid, review; Systems for Nuclear Auxiliary Power (SNAP-2) ---coolant boiling research for; Nuclear Power Plants ---development research on thermionic, Los Alamos Molten Plutonium Reactor Experiments ---fuel element analysis; Heat Transfer Systems ---conference on liquid metal; Bearings --coating for liquid metal, performance of; Systems for Nuclear Auxiliary Power (SNAP-8) ---component development; Sodium---heat transfer research on; Mercury --heat tr… more
Date: April 1, 1963
Creator: Dwyer, O. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experimental Determination of Corrections to the Neutron Activation of Gold Foils Exposed in Water

Description: The corrections required to deduce unperturbed neutron fluxes from measurements with foil absorbers were determined experimentally for the case of gold foils exposed in a light-water medium. The results are in good agreement with the theoretical predictions of Dalton and Osborn and of Ritchie and Eldridge. (auth)
Date: April 1, 1963
Creator: Zobel, W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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RADIATION SAFETY AND CONTROL AT THE OAK RIDGE NATIONAL LABORATORY, 1960- 1962

Description: Activities of the radiation safety program at Oak Ridge National Laboratory for the period 1960-1962 are described. A reduction in the frequency of radiation accidents was observed and a training program for technical and nontechnical personnel has been formulated. Sixteen facilities were improved to ensure safe operation at a cost of approximately 388,589. A comprehensive Radiation Warning and Communication System is being installed in three phases over a period of three years ending in FY 196… more
Date: April 1, 1963
Creator: Bruce, F.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Tensor Code

Description: The program, TENSOR, for the calculation of underground explosion phenomena and other time dependent problems involving the motion of elastic, plastic, fractured, and fluid materials is discussed. The method used in the code allows treatment of transient phenoraena in two space dimensions (cartesian or axial symmetry), and is particularly appropriate for problems involving compressible flow, large displacements, and free transitions of material between the elastic, cracked, plastic, and fluid s… more
Date: April 1, 1963
Creator: Maenchen, G. & Sack, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The Effect of Irradiation on the Hydrolysis of Uranium Carbides. I. Preparation of Uranium Monocarbide Pellets for Irradiation

Description: The effect of irradiation on the hydrolytic behavior of uranium monocarbide as related to the aqueous chemical processing of these reactor fuels is being investigated. The fabrication, evaluation, and encapsulation of the UC in niobium prior to irradiation is described. Uranium monocarbide buttons were prepared by arc-melting 1.51%enriched uranium metal with the stoichiometric quantity of spectroscopic-grade carbon. The buttons were then remelted and drop- cast into graphite thimbles 3/8 in. di… more
Date: April 1, 1963
Creator: Bradley, M.J.; Ferris, L.M.; Hikido, T. & Ullmann, J.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SNAP PROGRAMS-UPPER ATMOSPHERE EXPERIMENTAL RE-ENTRY STUDY. Final Summary Report

Description: An experimental flight test was made to verify and improve the methods and techniques used to predict the aerothermodynamic effects on re-entering SNAP devices. The amount of aerodynamic heating as a function of body shape, size, and mode of entry was indicated. Test specimens yielded trajectory, aerodynamic heating data, heat distribution, and heat transfer of known bodies. IBM 7090 digital programs were utilized and so constructed that one digital code complemented the other, i.e., at any tim… more
Date: April 1, 1963
Creator: Hagis, W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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SNAP AEROSPACE SAFETY PROGRAM. Quarterly Technical Progress Report, October-December 1962

Description: Progress made during the period is reported including analyses of experiments and tests, and evaluation of effort. The subject material concerns reactor transient and excursion tests, fission product release studies, end-of- life shutdown devices, critical configuration studies, mechanical and thermochemical effects, reactor separation and fuel element ejection, and reentry burnup of fuel elements. The design of the SNAPTRAN 2/10A-1 and -2 machines was essentially completed and fabrication of m… more
Date: April 1, 1963
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

DIRECT REDUCTION OF URANIUM HEXAFLUORIDE TO URANIUM METAL WITH SODIUM

Description: Thermodynamic considerations indicate that sodium should be favorable for the one-step reduction of UF/sub 6/ to uranium metal. A reaction vessel was developed for the continuous reduction of UF/sub 6/ to metal with batch collection of the products, and several experimental tests established the chemical feasibility of this direct and continuous reduction. Up to 93.5% of the uranium content of UF/sub 6/ continuously reduced by sodium in a reaction vessel was recovered as massive uranium metal i… more
Date: April 1, 1963
Creator: Scott, C.D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Description and Proposed Operation of the Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II)

Description: The Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR- II), the process equipment, and the operations to be conducted in the facility are described. The Fuel Cycle Facility is a plant for reprocessing, by pyrometallurgical methods, the core and blanket material discharged from EBR-II. The reactor core alloy is uranium-5% fissium and contains about 46 wt.% U/sup 235/ . The blanket material consists of U in which plutonium is bred. Core and blanket subassemblies contained in tr… more
Date: April 1, 1963
Creator: Hesson, J. C.; Feldman, M. J. & Burris, L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Cycle Program. A Boiling Water Reactor Research and Development Program. Eleventh Quarterly Progress Report, January-March 1963

Description: Even though VBWR shutdowns were required for location and removal of five failed fuel assemblies (HPD Program), the increase in fuel exposure was good. Fuel exposures wili pass the values at which cold worked stainless steel cladding was failing under the HPD Program. Failure of the 0.005-inch cold worked stainless steel clad fuel rods in assembly 8L was traced to strain cycling fatigue. A study of tapered fuel rods indicates a potential advantage for us of a variable water/fuel ratio along the… more
Date: April 1, 1963
Creator: Howard, C.L. comp.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Mathematical Model for an Associative Memory

Description: A mathematical model for an associative memory is proposed that uses associative addressing and distributed storage. Associative addressing is accomplished by mapping from a space with relatively few dimensions (input variables) to the vertices of a binary-valued hypercube embedded in a much higher dimensional space. The dimension of the image space is chosen to be sufficiently grent that a hyperplane can be passed through the origin such that the relative distances to the image points are the … more
Date: April 1, 1963
Creator: Simmons, G.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Self-Consistent Models of Strong Interaction With Chiral Symmetry

Description: Some simple models of (renormalizable) meson-nucleon interaction are examined in which the nucleon mass is entirely due to interaction and the chiral ( gamma /sub 5/) symmetry is broken'' to become a hidden symmetry. It is found that such a scheme is possible provided that a vector meson is introduced as an elementary field. (auth)
Date: April 1, 1963
Creator: Nambu, Y. & Pascual, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PIQUA-ELK RIVER REACTORS SPENT FUEL SHIPPING CASK. Final Design Report

Description: >The Piqua-Elk River spent fuel shipping cask, designed to transport 19 fuel assemblies from either reactor starting 120 days after reactor shutdown for refueling, is described. The maximum weight of the ioaded cask is 30 tons and the dimensions are 55 in. dia x 108 in. high. The space envelope required for the cask and shipping structure is 7 x 10 x 10 ft. The cask system is composed of 6 major components: cask body, closure head, fuel basket, shipping structure, lifting yoke, and Elk River fu… more
Date: April 1, 1963
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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MARITIME REACTOR PROGRAM. Annual Progress Report for Period Ending November 30, 1962

Description: A survey of the,N. S. Savannah reactor shield was carried out during the report period. The results showed that the shield effectively meets design specifications. Tests of 12 removal by a charcoal unit in the N. S. Savannah reactor emergency ventilation system using 80 to 90% water-saturated air showed a unit efficiency of 99.86 plus or minus 0.07% at the 95% confidence level. Simplified procedures were devised for using shipboard equipment to screen personnel suspected of having body burdens … more
Date: April 1, 1963
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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URANIUM(IV) NITRATE AS A REDUCING AGENT FOR PLUTONIUM(IV) IN THE PUREX PROCESS

Description: Practical procedures were demonstrated for partitioning plutonium from uranium in the Purex process with hydrazine-stabilized uranium(IV) nitrate as the reducing reagent for plutonium. Typical partitioning results were 0.04--0.2% loss of plutonium to the uranium product and less than 1 wt% uranium in the plutonium product. With uranium(IV) nitrate as a replacement for ferrous sulfamate, most solids in wastes from the Parex process can be eliminated. No undue hazard is expected from the use of h… more
Date: April 1, 1963
Creator: Schlea, C. S.; Caverly, M. R.; Henry, H. E. & Jenkins, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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