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Production of Single Crystal Copper Films at Low Temperatures

Description: A method is described for the production of single‐crystal films of copper at temperatures as low as −40°C. This method utilizes the epitaxy of copper on rock salt. A thin layer of copper is evaporated on a single crystal of salt at 350°C. Then a thick layer is evaporated at the low temperature. Films grown by this method have been examined using x‐ray and etching techniques. It was found that some of these films had single‐crystal regions of 1 mm diameter and larger. These crystallites had [10… more
Date: April 1959
Creator: Yelon, Arthur
Partner: UNT Libraries Government Documents Department
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Preliminary Report on 2% U235-Enriched UF4-C25H52 Critical Assemblies

Description: A series of critical experiments with blocks of 2% U235-enriched UF4-C25H52 has been initiated at the ORNL Critical Experiments Facility. Thus far assemblies with H:U235 atomic ratios of 195 and 294 have been built in parallelepipedal and simulated cylindrical geometries, both reflected and unreflected. From the results the minimum critical masses for reflected spheres have been determined to be 16.3 and 8.5 kg of U235 for fuel mixtures with H:U235 atomic ratios of 195 and 294, respectively. Th… more
Date: April 22, 1959
Creator: Mihalczo, J. T.; Lynn, J.J.; Scott, Dunlap & Connolly, W. C.
Partner: UNT Libraries Government Documents Department
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A Report on Dissolved O2 in the Primary Coolant of the Ker Loops

Description: A series of tests conducted in an attempt to reduce the observed O2 content of primary recirculation loop water to a value of <0.14ppm by the current loop method which is a combination of pressurizer degasification and venting flow.
Date: April 15, 1959
Creator: Eikum, Leon M.
Partner: UNT Libraries Government Documents Department
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Thermal Contact Conductance of Fuel Element nateriasls

Description: Thermal Resistance of the contact between to core and the jackets or unbonded fuel elements may easily be the largest source of error in core temperature predictions. The object of this work is to improve contact conductance predictions by measuring conductance of the joint between reactor fuel and cladding materials at joint pressures, temperatures and thermal flux levels approaching reactor service conditions.
Date: April 10, 1959
Creator: Wheeler, Robert G.
Partner: UNT Libraries Government Documents Department
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Shielding of PRTR Gas Loop & Filter

Description: "The PRTR Pressured Gas-Cooled Loop Facility, or Gas Loop, is an experimental facility to be installed in the Plutonium Recycle Test Reactor for use in studies contributing to advancement of the technology of gas-cooled reactors. The facility will provide an in-reactor loop for studying phenomena occurring under conditions likely to exist in gas-cooled reactors.
Date: April 23, 1959
Creator: Reginmbal, J.J.
Partner: UNT Libraries Government Documents Department
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Uranium Cold Extrusion

Description: Several hollow uranium cores of "C" size I & E diameters were fabricated by cold extrusion (550 to 750 F) at Hunter Douglas Aluminum Corporation. Results show diameter control and reproducibility are excellent. Preferred orientation induced by this process is completely removed by a single standard beta heat treatment.
Date: April 21, 1959
Creator: Riedeman, G. W.
Partner: UNT Libraries Government Documents Department
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An Automatic Water Deaeration System

Description: Laboratory studies involving fluid flow through porous media require use of fluids having low dissolved gas content. Water is the major fluid used in various and box model and soil permeability studies carried out by the Geochemical and Geophysical Research group. Tap water supplied to the 222-U Bldg. contains a large amount of dissolved air. Under the reduced pressure encountered during model studies, the air is released from solution and gradually clogs the pores of the sand or other porous m… more
Date: April 20, 1959
Creator: Raymond, J. R.
Partner: UNT Libraries Government Documents Department
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Division of Reactor Development Programs Monthly Report- March 1959

Description: Basic Studies. It has been reported previously that mixed crystals of PuO2 and UO2 have a higher sintering rate than UO2 alone. However, results to the contrary were obtained on addition to 1/4, 1/2, 1, 2, 5, and 10 w/o PuO2 to PWR grade UO2. Pellets of the above concentrations were heated for one hour in hydrogen at 100 C intervals from 1000 to 1600C.
Date: April 15, 1959
Creator: Hanford Laboratories Operation Fuels Preparation Department, Irradiation Processing Department
Partner: UNT Libraries Government Documents Department
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Water Temperatures for the Columbia River Above the Hanford Reactors, September, 1946 Through December, 1958

Description: The ambient temperature of the Columbia River is of interest to the Aquatic Biology Operation since it provides a basis for controlling the temperatures in various experimental tanks which contain Columbia River organisms and since it provides some indication of whether conditions are favorable for the valuable species of fish living in the river. Since the start-up of the plant, temperatures of the river water have been taken in the several water treatment plants.
Date: April 15, 1959
Creator: Foster, R. F.
Partner: UNT Libraries Government Documents Department
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Multi-Region Simulation of Xenon Poisoning in the PRTR

Description: A previous study has been completed on the buildup and decay of xenon poisoning in the PRTR by simulating the reactor as a single region. The results of this study indicated that a study using a more refined model of the reactor would be valuable.
Date: April 13, 1959
Creator: Cameron, W. D.
Partner: UNT Libraries Government Documents Department
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ETR-MTR Experiments on Restraint of Uranium Swelling by Zirconium Cladding

Description: In conjunction with the fuel element development program at Hanford, it is desired to determine the effects of cladding and core temperatures, cladding thickness, and exposure upon the swelling behavior of unalloyed uranium. To obtain this information, it is proposed to irradiate several fuel rods, clad by coextrusion with Zr-2, in NeK filled stainless steel capsules. The central uranium temperatures are to be monitored by axial thermocouples. Irradiation tests in the MTR and ETR using capsules… more
Date: April 10, 1959
Creator: Weber, J. W.
Partner: UNT Libraries Government Documents Department
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Removal and Recovery of Plutonium from Recuplex Process Waste by Anion Exchange

Description: Crib evaluation studies showed the soil uptake of plutonium from the Recuplex process (CAW) waste to be low. Preliminary studies of the low soil adsorption of plutonium revealed the presence of a plutonium nitrate anion complex which could be removed by adsorption on a strong base anion exchange resin.
Date: April 10, 1959
Creator: Nelson, J. L.
Partner: UNT Libraries Government Documents Department
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Development and Preliminary Testing of Powder-Lock Feeder

Description: At the request of 234-5 Development, studies of a system for controlling plutonium powder transfer were undertaken by Process Equipment Development. This report presents details of equipment designed to fulfill requirements and proposes equipment for installation on additional Hot Button Line prototypes.
Date: April 3, 1959
Creator: Dunn, J.
Partner: UNT Libraries Government Documents Department
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Remote Area Scintillation Monitoring System

Description: This report was written to describe briefly several possible variations of such systems along with probable cost estimates. Previous work has been shown that the application of scintillation detectors is the simplest and most reliable means for such monitoring. By proper detector selection and measuring methods, the system can be of an approximate gamma dose-rate with gamma energy independence above about 100 Kev. The same system using detector change only is directly applicable to beta, gamma,… more
Date: April 21, 1959
Creator: Spear, W. G.
Partner: UNT Libraries Government Documents Department
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Corrosion of 2R-2 and 304 Stainless Steel Following the Turco-4501 Decontamination Process.

Description: The build up of contaminated film on the internal surfaces of high temperature in-reactor recirculating water loops has created serious radiation exposure problems to operational and maintenance personnel. A considerable amount of work has been applied to develop an effective decontamination process for the decontamination of these loops and their components.
Date: April 20, 1959
Creator: Larrick, A. P. & Lotsinger, R. J.
Partner: UNT Libraries Government Documents Department
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Heat Transfer Study for Self-Boiling Radioactive Wastes

Description: The temperature characteristics associated with the handling of self-boiling radioactive wastes from the separations extraction processes in the Chemical Processing Department have necessitated several heat transfer studies. Earlier studies 1,2,3 defined the feasibility of self-concentration in existing waste storage facilities by determining the rate of heat generation from the decay of stored fission products and by defining the rate of heat loss from existing storage tanks to the surrounding… more
Date: April 27, 1959
Creator: Stivers, H.W. & Taylor, H.W.
Partner: UNT Libraries Government Documents Department
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PRTR Gas-Cooled Loop, Hazards Survey of Preliminary Scope Design

Description: The Atomic Energy Commission has recently developed an enlarged program for the study of graphite moderated, gas cooled power reactor systems. It has been recognized, however, that understanding of radiation damage and radiation induced chemical reactions of graphite at the proposed high moderator temperatures is inadequate and that improved understanding is essential if the design of such reactors is to be optimized. Accordingly, the Atomic Energy Commission requested Hanford to organize a mod… more
Date: April 20, 1959
Creator: Wittenbrock, N. G.
Partner: UNT Libraries Government Documents Department
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The Stability of Three Base Metal Thermocouples in Helium-Carbon Dioxide, Carbon Dioxide and Air at 300 C

Description: In support of an in-reactor thermocouple stability testing program now in progress, laboratory studies were made relative to the stability of thermocouple bundles similar to those projected for in-reactor use. Two sets of chromel-alumel, copper-constantan and iron-constantan thermocouples were held for extended periods at 300 C in successive atmospheres of 75% helium-25% carbon dioxide. 100% carbon dioxide and air. Thermocouple stability was verified by measuring emf's at the freezing point of … more
Date: April 14, 1959
Creator: Sako, J. H.
Partner: UNT Libraries Government Documents Department
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The Radiochemistry Of Thorium

Description: This report was prepared at the request of the Subcommittee on Radiochemistry of the Committee on Nuclear Science of the National Research Council as a contribution to a proposed master file on the radiochemistry of all the elements. All known material on the radiochemistry of thorium is included in this report.
Date: April 1959
Creator: Hyde, Earl K.
Partner: UNT Libraries Government Documents Department
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The Cross Section For Compound-Nucleus Formation In Heavy-Ion-Induced Reactions

Description: With the increasing availability of accelerators capable of producing beams of heavy ions it has become useful to know the cross section for a heavy ion to form a compound nucleus by interaction with a target nucleus. The results of calculations based on two simple models are presented here in order to give some idea of the magnitude of this cross section as a function of the energy of the bombarding particle.
Date: April 1959
Creator: Thomas, T. Darrah
Partner: UNT Libraries Government Documents Department
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Measurement Of Average Neutron Energies For (o, n) Neutron Sources

Description: A method is presented for measuring the average energy of the neutrons from a source. The attenuation of the neutrons by polyethylene is measured by the use of a long counter in good geometry. The attenuation length is a sensitive function of the neutron energy. The average neutron energies from several (o, n) sources have been measured and agree well with values obtained by other techniques.
Date: April 1, 1959
Creator: Hess, Wilmot N. & Smith, Alan R.
Partner: UNT Libraries Government Documents Department
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Filling Instructions for the Pratt & Whitney Forced Convection Liquid Metal Inpile Loop Experiment (PW19)

Description: The apparatus and procedures that are to be used to fill the liquid metal system of the Pratt and Whitney Forced Convection Liquid Metal Inpile Loop are described. The liquid metal to be used is a mixture containing 56% Na and 44% K, which is a liquid at room temperature. In order to simplify the filling procedure at the reactor site, two containers, each of which contains exactly enough liquid metal to fill the experiment to the prescribed level, a fill dolly incorporating a purified helium sy… more
Date: April 29, 1959
Creator: Heyl, P. T.
Partner: UNT Libraries Government Documents Department
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Uranium Exploration and Development in Argentina

Description: Report discussing initial ventures in a joint project between the United States Atomic Energy Commission and the Comision Nacional de la Energía Atomica of Argentina (CNEA) to examine existing uranium deposits in Argentina and determine the best course for new prospecting programs. This document outlines the findings for specific locations visited in Argentina and their relative importance.
Date: April 1959
Creator: Stocking, Hobart E.; Wood, H. B. & Keyes, W. W.
Partner: UNT Libraries Government Documents Department
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