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Preliminary Hazards Summary Report For The Vallecitos Superheat Reactor

Description: This Preliminary Hazards Summary Report has been prepared for submission to the United States Atomic Energy Commission in compliance with Part 50 of the regulations governing the licensing of production or utilization facilities, pursuant to the Atomic Energy Act of 1954, as amended, and contains the general information required by 10 CFR 50.34.
Date: February 1, 1961
Creator: General Electric Company
Partner: UNT Libraries Government Documents Department
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A standard AlSi braze wetting test for aluminum components used in the lead-dip process

Description: Wetting of the aluminum components by aluminum-silicon brazing alloy is a major factor influencing the quality of the fuel elements. Several process variables associated with the impact extrusion of aluminum components influence the resulting Al surface. In addition, these processing variables interact with the HAPO component production cleaning process to give varying results. Purpose of this document is to define the parameters for selecting, preparing) testing and evaluating the AlSi wetting… more
Date: February 1, 1961
Creator: Burgess, C. A.
Partner: UNT Libraries Government Documents Department
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HRT CORROSION SAMPLES--ADDITIONAL DATA ON SPECIMENS REMOVED PRIOR TO RUN NO. 20

Description: Results of the examinations of corrosion specimens exposed in the HRT are presented. Specimens examined include core screen samples, core specimen array No. 1, blanket specimen array No. 2, core solution line specimen arrays No. 103 and 103A, and blanket solution line specimen array No. 203. These data include corrosion rates, computed from specimen weight-changes, and results of chemical analyses of scales removed from the specimens or specimen holders. A summary is included of the HRT operati… more
Date: February 1, 1961
Creator: Baker, J.E.; Silverman, M.D.; Jenks, G.H. & Olsen, A.R.
Partner: UNT Libraries Government Documents Department
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EBR-II Dry Critical Experiments. Experimental Program, Experimental Procedures and Safety Considerations

Description: Revisions in the reactor system and operating procedures necessary for carrying out a proposed dry critical experiment in the EBR-II are described. The safety aspect of the program is considered. The critical experiment will be conducted in the EBR-II prior to filling the primary system with sodium. The facility, experimental program, operational and experimental procedures, and hazards and plant safety are described. (M.C.G.)
Date: February 1, 1961
Creator: Kock, L. J.; Loewenstein, W. B.; Lovoff, A.; Hooker, H. H.; Monson, H. O.; Ramp, R. L. et al.
Partner: UNT Libraries Government Documents Department
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Isotopic Sources of Secondary Radiation. Final Report

Description: Recent work on isotopic x ray sources is reportcd. The research was directed toward optimization of high-level isotopic sources and evaluation of their use in typical scientific and technical applications. The resulting experi- mental data are used in obtaining an approximate mathematical formulation of x- ray output as a function of beta energy, target mnaterial, and source configuration. (J.R.D.)
Date: February 1, 1961
Creator: Filosofo, I.
Partner: UNT Libraries Government Documents Department
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Synthesis and Fabrication of Refractory Uranium Compounds. Summary Report for May 1959 Through December 1960

Description: Activitiee are described in an investigation to develop refractory U materiala for superior reactor fuels. Uranium carbide was prepared by cold pressing in pellets with densitier of 92 to 96% of theoretical. Uranium nitride was synthesized, and it was found that dense specimens (95% of theoretical) could be obtained in N-deficient powder, however in stochiometric compositions the maximum density obtained was 85% of theoretical. In other work dense uranium silicide was prepared and several prope… more
Date: February 1, 1961
Creator: Taylor, K. M. & McMurtry, C. H.
Partner: UNT Libraries Government Documents Department
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Equations of State for Evolution Studies of Supernovae

Description: Tables of the energy, pressure, and chemical composition for a stellar mixture, originally a pure Fe/sup 56/, are presented as functions of temperature and density. They cover a range of conditions pertinent to the evolution of supernovae, involving the deconiposition of iron into helium plus neutrons, and the later stage of decomposition of helium into neutrons and protons. Relativistic degeneracy of electrons is included in these calculations. (auth)
Date: February 1, 1961
Creator: Grasberger, W. H. & Yeaton, J. B.
Partner: UNT Libraries Government Documents Department
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THE HEAT TREATMENT OF PLUTONIUM

Description: Two groups of plutonium bars, one group containing 165 ppm iron and the other 678 ppm iron were end-quenched from the beta, gamma, delta, delta-prime, and epsilon phases. In general, cooling rate was found to have three striking effects on microstructure. The alpha grain size was found to decrease with increasing cooling rate during cooling from all phases. Upon cooling high-iron plutonium from the epsilon phase, the size of the Pu--Pu6/sub 6/Fe eutectic network decreased with increasing coolin… more
Date: February 1, 1961
Creator: Gardner, H.R.
Partner: UNT Libraries Government Documents Department
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Hazards Summary Report on the Juggernaut Reactor

Description: The Juggernaut is a light-water-cooled and moderated, graphite- reflected, heterogeneous thermal reactor designed to provide experimental facilities for conducting basic research in the neutron flux range to 4 x l0 n/cm/ sec at an operating power level of 250 kw(t). Pertinent design and operating characteristics are tabulated. Evaluations are made for potential hazards posed by certain hypothetical major accidents during the operation, and the adequacy of the safeguards provided to insure that … more
Date: February 1, 1961
Creator: Folkrod, J. R.; Moon, D. P. & Saluja, J. F.
Partner: UNT Libraries Government Documents Department
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Development of Methods for the Refabrication of Ebr-Ii Fuel Elements. Part I. Engineering Considerations for Ebr-Ii Fuel Refabrication. Part Ii. Development of Injection Casting Methods and Equipment. Part Iii. Development of Fuel Pin Processing Methods and Equipment. Part Iv. Assembly, Welding, and Leak Testing Ebr-Ii Fuel Rods. Part v. Dodium Bonding and Bond Testing Ebr-Ii Fu

Description: The development of remote fabrication methods and equipment in which the cooling periods, chemical fission product separation, and complete decontamination of the fuel is not required is discussed. A process designed around precision casting in multiple, glass molds served as a basis for design of refabrication equipment. The injection casting process is used. Procedures and equipment were developed for the remote manufacture of right-cylindrical, uranium alloy fuel pins from the castings. Asse… more
Date: February 1, 1961
Creator: Shuck, A. B.; Ayer, J. E.; Jelinek, H. F.; Iverson, G. M.; Carson, N. J. Jr.; Brak, S. B. et al.
Partner: UNT Libraries Government Documents Department
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METALLURGY OF ZIRCALOY-2. PART II. THE EFFECTS OF FABRICATION VARIABLES ON THE PREFERRED ORIENTATION AND ANISOTROPY OF STRAIN BEHAVIOR

Description: The preferred orientation and anisotropy of strain behavior of Zircaloy- 2 were studied as functions of fabrication variables. An inverse-pole-figure technique was used for the preferred orientation determinations. Evaluation of the effects of the fabrication variables on the anisotropy of strain behavior was accomplished by a contractile strainaxial strain analysis. An analysis of strain behavior in the normal direction was developed on the basis of theory of plastic flow of anisotropic metals… more
Date: February 1, 1961
Creator: Rittenhouse, P.L. & Picklesimer, M.L.
Partner: UNT Libraries Government Documents Department
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BUILDUP OF Cf$sup 252$ AND INTERMEDIATE ISOTOPES FROM Cm$sup 244$ IN A HIGH FLUX

Description: The amount of Cf/sup 252/ and intermediate isotopes which could be made from Cm/sup 244/ in a reactor with high neutron flux was calculated. The variations of different isotopes formed in the bombardment as a function of time are described by a series of linear differential equations. The cross sections used were either weighed measured values or values estimated from the amounts of curium and californium isotopes formed in irradiations of heavy elements. The number of atoms of heavy curium iso… more
Date: February 1, 1961
Creator: Vandenbosch, S.E. & Fields, P.R.
Partner: UNT Libraries Government Documents Department
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A Condenser for the Vacuum Distillation of Metals

Description: A condenser, suitable for use in the distillation of metals was designed. The temperature of the condensing surface was established by controlling the pressure over boiling NaK-78 contained within the condenser. Performance was evaluated in test units in which pure bismuth was distilled as the test metal. (auth)
Date: February 1, 1961
Creator: Burnet, G. & Buchanan, W.
Partner: UNT Libraries Government Documents Department
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OXIDATION OF URANIUM(IV) BY OXYGEN AND NITROUS ACID

Description: The oxidation of uranium(IV) by oxygen and nitrous acid was studied in both 30% TBP-""Ultrasene"" and in aqueous solutions. Emphasis was placed on reactions between uranium(IV) and nitrous acid. Distribution coefficients were measured for uranium(IV) and uranium(VI) in the nitric acid-30% TBP system. The use of uranium(IV) as a reductant for plutonium in the Purex process is discussed. (auth)
Date: February 1, 1961
Creator: Slade, A. Laird
Partner: UNT Libraries Government Documents Department
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Separations by Solvent Extraction With Tri-n-octyl-Phosphine Oxide

Description: A compilation was made of extraction data obtained for tri-n- octylphosphine oxide (TOPO). Diluents, oxidation states of the elements, type and concentration of acid, concentration of the metal and extractant, phase volumes, temperature, phase equilibrium, stripping, decomposition of metal adducts, and determination of extracted elements are discussed. lts extraction characteristics for the elements in each pericdic group are described. (M.C.G.)
Date: February 1, 1961
Creator: White, J. C. & Ross, W. J.
Partner: UNT Libraries Government Documents Department
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MUFT-5--A FAST NEUTRON SPECTRUM PROGRAM FOR THE PHILCO-2000

Description: The program was written for the Philco-2000 computer to provide a nuclear design computing tool equivalent to the IBM-704 computer program MUFT-4 and to provide a set of routines for a future spatial multigroup program, P/sub 3/ MG-1. In addition to the features of its 704 predecessor, MUFT-5 provides a more complete isotopic edit, an optional blackness coefficient edit, and the use of a complete P/sub i/->i>s library. The resultant program is found to be easier to use because of the simplicity… more
Date: February 1, 1961
Creator: Bohl, H. Jr. & Hemphill, A.P.
Partner: UNT Libraries Government Documents Department
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The Effect of Irradiation on Siliconized-Silicon Carbide Coatings for Graphite

Description: The results of an investigation into the effect of irradiation on the quality and integrity of several commercial siliocnized-silicon carbide (Si-- SiC) coatings for graphite are summarized. Si-- SiC-- coated graphites were oxidationtested at 1000 deg C in air both before and after irradiation. Data show that base graphites for coating must be fairly isotropic and must be stable toward high temperature radiation damage if the coating is to survive in-reactcr conditions. (auth)
Date: February 1, 1961
Creator: Jackson, J. L.
Partner: UNT Libraries Government Documents Department
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Engineering Applications of Analog Computers

Description: Six examples are given of the application of analog computers in the fields of reactor engineering, heat transfer, and dynamics: deceleration of a reactor control rod by dashpot, pressure variations through a packed bed, reactor kinetics over many decades with thermal feedback (simulation of a TREAT transient), vibrating system with two degrees of freedom, temperature distribution in a radiating fin, and temperature distribution in an irfinite slab with variable thermal properties. (D.L.C.)
Date: February 1, 1961
Creator: Bryant, L. T.; Janicke, M. J.; Just, L. C. & Winiecki, A. L.
Partner: UNT Libraries Government Documents Department
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A CONTRIBUTION TO THE STUDY OF THE REDUCTION OF UF$sub 4$ TO URANIUM METAL

Description: Reduction of small charges of uranium tetrafluoride with magnesium proved to be successful. By hand-tamping of UF/sub 4/-- Mg blend, tap densities ranglng between3.1 and 3.4 g/cc were obtained. The reduction yields for these densities ranged from 72.79 to 93.71%. In the case of machinecompacted UF4-- Mg blend having tap densities from 3.58 to 3.68 g/cc, reduction yields were higher, ranging between 91.45 and 97.2%. Machine-compacted blends gave much more uniform temperature distribution curves … more
Date: February 1, 1961
Creator: Milosavljevich, J. & Baird, J.
Partner: UNT Libraries Government Documents Department
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A TEMPERATURE DISTRIBUTION ANALYSIS ALONG A THERMAL RADIATING FIN OF NONUNIFORM THICKNESS

Description: The general differential equation of a thermally radiating fin is presented for the situation of a uniform heat source along the base of the fin. An electronic analog solution of a fin of nonuniform thickess with one- dimensional steadystate radiant heat transfer is presented. The specific example is concerned with a constant rate of variation of thickness; however, any general configuration could be used. (auth)
Date: February 1, 1961
Creator: Janicke, M.J. & Just, L.C.
Partner: UNT Libraries Government Documents Department
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The Practical Application of Space Nuclear Power in the 1960's

Description: Nuclear reactor space electric power units under development in the U. S. include the SNAP-2, SNAP-8, and SNAP-10. The electric power output of these Systems for Nuclear Auxiliary Power (SNAP) extends over three decades of power, from 300 watts to 6O kilowatts. The major operational, installation, and handling characteristics of these nuclear power units are described. In particular, some limitations and restrictions with regard to payload, shielding, and radiation environment are described wit… more
Date: February 1, 1961
Creator: Wetch, J.R.; Dieckamp, H.M. & Anderson, G.M.
Partner: UNT Libraries Government Documents Department
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