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Completion Report An Automatic Fuel Element Stamping Machine

Description: This document will be concerned with the design, operation and maintenance of an automatic fuel element stamping machine. In order to take advantage of automatic unloading and length checking at the Acme-Gridley lathes in the 313 Building, automatic stamping of fuel elements is desirable. This, along with the need for a permanent canning line identification, resulted in a request for a machine to automatically stamp HAPO fuel elements on a production basis.
Date: January 12, 1960
Creator: Allen, C. H.
Partner: UNT Libraries Government Documents Department
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Final Report of Piping Components for Organic Coolants

Description: Organic compounds with high boiling points and low corrosion qualities have been considered for use as reactor coolants and moderators. Those being considered, however, have a greater tendency to leak than does water. A program to evaluate mechanical closures to be used for a leak-tight system for organic fluids has been established. Report HW-59446 covered descriptions of the facility used in this study and the primary results of tests covering two liquids, fittings, and instrumentation. This … more
Date: January 12, 1960
Creator: Floyd, H. L.
Partner: UNT Libraries Government Documents Department
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Molten-Salt Breeder Reactors

Description: The problems involved in building a molten-salt thermal-breeder reactor are reviewed, and it is concluded that the most feasible construction is an externally-cooled reactor with the fuel salt passing through the reactor core in graphite tubes.
Date: January 12, 1960
Creator: MacPherson, H. G.
Partner: UNT Libraries Government Documents Department
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Once Through Decontamination Studies- Interim Report No. 1.

Description: The decontamination of the present Hanford reactors involves a once-through cleaning operation. Considerable interest has also been shown in determining the feasibility of this once-through technique for cleanup of certain portions of the NPR system. This report contains information on a series of tests performed in the 242-B single pass flow facility. Information concerning the following are presented: (1) Efficiency of decontaminating KER Loop 1 and 2 contaminated specimens. (2) Efficiency of… more
Date: January 12, 1960
Creator: Perrigo, L. D. & Hekenson, J. F.
Partner: UNT Libraries Government Documents Department
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Operation Pre-Gnome: Seismic Data from Natural Phenomena and High-Explosive Tests Near Carlsbad, New Mexico

Description: Formulas derived from earlier work satisfactorily predicted low frequency ground effects resulting from the Pre-Gnome explosions, but they not predict high accelerations associated with high frequency ground waves. The Pre-Gnome experiments taken since indicated that accelerations and ground amplitudes are proportional to the explosive charge, but physical conditions limit extrapolation on this basis to relatively low yields. Predicted accelerations resulting from the 10 kt Gnome explosion in p… more
Date: January 12, 1960
Creator: Carder, Dean S.; Murphy, L. M.; Cloud, W. K. & Pearce, T. H.
Partner: UNT Libraries Government Documents Department
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Proposed Modifications to HRE-2 Core

Description: As a result of flow tests of a full-scale HRT flow model, it is proposed to modify the core flow by removing 5 or more screens, plugging the hole and reversing the direction of flow. This will provide better cooling and mechanical scrubbing of the core wall. A procedure for flushing solids out of the core was developed.
Date: January 12, 1960
Creator: Lawson, C. G.
Partner: UNT Libraries Government Documents Department
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Rainout Containment

Description: An evaluation of the efficiency of a sprinkler system as an airborne fission product containment mechanism Is presented. The primary inadequacies and objections to such a system are outlined and data on droplet efficiencies are included. (J.R.D.)
Date: January 12, 1960
Creator: Wegmann, G. L.
Partner: UNT Libraries Government Documents Department
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Disposition of Contaminated Processing Equipment at Hanford Atomic Products Operation 1958-1959

Description: Operating plant experiences in restoring to useful service failed equipment contaminated through exposures to radioactive processes is of international interest to the nuclear industry. In accordance with a request from the Hanford Operations Office of the United States Atomic Energy Commission this report of the various measures taken in rehabilitating for re-use expensive engineered equipment has been compiled by the General Electric Company. This report is a review and summary of the dispos… more
Date: February 12, 1960
Creator: Kingsley, P. S.
Partner: UNT Libraries Government Documents Department
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Energy release per fission in the Hanford reactors

Description: The average energy release per fission event in a reactor is dependent on the composition and arrangement of the lattice materials. In a study of heat generation in the NPR, Nilson developed expressions for calculating the average energy released in each material per fission event. These relationships have been used in the present calculations to obtain the energy release per fission in existing Hanford reactors.
Date: February 12, 1960
Creator: Morgan, W. C. & Bunch, W. L.
Partner: UNT Libraries Government Documents Department
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PURIFICATION OF PROMETHIUM BY LIQUID-LIQUID EXTRACTION

Description: A process was developed for separating promethium from raixed fisBion product rare earths by continuous multistage conntercurrent extraction with 100% tri-nbutylphosphste from nitric acid of 12 N or higher concentration. Distribution coefficients at 12 N acidity for aecdamium. promethium. and samarium are 0.43. 0.82, and 1.55, respectively. Single-stage separation factors of 1.9 between successive elements can be maintained throughout the system to give separations dependent only on the number … more
Date: February 12, 1960
Creator: Weaver, B. & Kappelmann, F.A.
Partner: UNT Libraries Government Documents Department
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REDUCTION OF CUPRIC OXIDE BY HYDROGEN. II. CONVERSION OF HYDROGEN TO WATER OVER FIXED BEDS

Description: The conditions under which hydrogen could be quantitatively recovered from mixtures of gases by oxidation over fixed beds of CuO were investigated. The conversion of H/sub 2/ to H/sub 2/O by reduction of CuO in fixed beds increased with in- creasing bed length, temperature, hydrogen/argon ratio, and decreasing mesh size of CuO. Residence times required for 99% conversion in a 1- in.-diam. bed were 0.6 and 1.2 sec for 30% hydrogen-70% argon and 10% hydrogen90% argon mixtures, respectively, at a … more
Date: February 12, 1960
Creator: Bond, W. D. & Clark, W. E.
Partner: UNT Libraries Government Documents Department
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HEAT-TRANSFER EXPERIMENTS ON A PROPOSED FUEL ASSEMBLY FOR THE EXPERIMENTAL GAS COOLED REACTOR. SECTION II FO FUEL-ASSEMBLY HEAT-TRANSFER AND CHANNEL PRESSURE-DROP EXPERIMENT FOR THE EGCR RESEARCH AND DEVELOPMENT PROGRAM

Description: Heat-transfer data are presented for the Experimental Gas Cooled Reactor Title I seven-rod fuel-assembly design. The effect on heat transfer of (1) the radial location of the outer six rods of the seven-fuel-rod cluster and of (2) the addition of helical-finned spacers at the midpoint of each of the seven fuel rods is discussed. The heattransfer data were obtained to verify preliminary general assumptions pertaining to the heat-transfer characteristics of the seven- rod fuel-assembly design and… more
Date: April 12, 1960
Creator: Beaudoin, C.L. & Higgins, R.M.
Partner: UNT Libraries Government Documents Department
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Spert Project. Quarterly Technical Report for April, May, June 1959

Description: SPERT I: The characteristics of the boiling process and its relatin to moderator expulsion in Spert I were investigated in a series of capsule type experiments. A fuel-bearing oapsule, instrumented to provide pressure, volume, and temperature data during transient power excursions, was placed in a high flux region of the Spert I P core. Five step-induced transients initiated from boiling indicate that the kinetic behavior of the stainless steel clad P-18/19 core is dependent on initial temperat… more
Date: April 12, 1960
Creator: Haire, J. C.
Partner: UNT Libraries Government Documents Department
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Development of Corrosion-Resistant Niobium-Base Alloys

Description: The hot-water corrosion resistance and mechanical properties of niobium and a number of its alloys were evaluated relative to their usefulness in pressurized-water thermal reactors. Unalloyed niobium was found to be rapidly attacked by 600 and 680 deg F water and 750 F steam. A number of alloying additions were found which markedly improve the corrosion resistance of niobium. Of these, binary and ternary combinations of chromium, molybdenum, titanium, vanadium, and zirconium were among the most… more
Date: May 12, 1960
Creator: Maykuth, D. J.; Klopp, W. D.; Jaffee, R. I.; Berry, W. E. & Fink, F. W.
Partner: UNT Libraries Government Documents Department
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Evaluation of External Holdup of Circulating Fuel Thermal Breeders as Related to Cost and Feasibility

Description: The external holdup of expensive materials and associated capital costs for the heat removal systems of fluid fuel breeders were determined. The aqueous homogeneous and molten salt breeders were found to contain substantially less uranium holdup external to the core than the liquid metal fueled breeder. The cost of heat removal and turbogenerator plant equipment for the three systems was compared. (auth)
Date: May 12, 1960
Creator: Spiewak, I & Parsly, L F
Partner: UNT Libraries Government Documents Department
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Photodisintegration Cross Section of Beryllium Near Threshold

Description: Abstract. The cross section of photoneutron production in Be9 at energies of 1.692, 1.720, and 1.78 Mev has been investigated using radioisotope gamma-ray sources. Neutron counting was by manganous sulfate bathe and a long counter. Gamma-ray counting was by a scintillation spectrometer consisting of a NaI(T1) scintillation crystal and a 256 channel pulse-height analyzer. A theoretical treatment of the P [right arrow] S transition near threshold using square-well potentials is also presented.
Date: May 12, 1960
Creator: Prosser, John M. & John, Walter, Jr.
Partner: UNT Libraries Government Documents Department
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Plutonium Oxide- Plastic Mixtures for Critical Mass Studies

Description: Critical mass experiments to be conducted at HAPO will require dilute and concentrated plutonium solutions. Since very high plutonium concentrations (~2,000 g/l) cannot be attained in pumpable solutions, solid plutonium compounds will be utilized for this phase of the work. Mixtures of plutonium oxide and polyethylene, methyl methacrylate or paraffin compacted in containers have been considers for use in highly-concentrated plutonium systems of known hydrogen to plutonium atomic ratio (H/Pu).
Date: May 12, 1960
Creator: Crocker, H. W.
Partner: UNT Libraries Government Documents Department
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The Bonding of Molybdenum-and Niobium-Clad Fuel Elements

Description: A solid-state bonding technique involving the use of gas pressure at elevated temperatures was utilized for the self-bonding of molybdenum and niobium. Bonding conditions and surface preparation as a function of the integrity of the bond achieved were evaluated for each material. Optimum self-bonding of niobium was achieved by bonding parameters of 2100 to 2300 deg F at 10,000 psi for 3 hr with surfaces which had been prepared by etching in a nitrichydrofluoric acid solution prior to bonding. T… more
Date: July 12, 1960
Creator: Paprocki, S. J.; Hodge, E. S. & Gripshover, P. J.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Chemical Development Section C Progress Report for April-May 1960

Description: An economical process was successfully demonstrated in bench-scale continuous equipment for stripping U from amines with ammonium carbonate solution. A continuous countercurrent mixer-settler extraction system was set up for further testing of the process for recovery of Te, Np, and U by tertiary amine extraction from UF/sub 6/ transfer cylinder was solutions. The effect of Purex aqueous feed adjustment procedures on Pu extraction by 1 M di-secbutyl phenylphosphonate (DSBPP) was studied. Work w… more
Date: July 12, 1960
Creator: Brown, K B
Partner: UNT Libraries Government Documents Department
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