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Amine Extraction of Plutonium From Nitric Acid Solutions Loading and Stripping Experiments

Description: Information is presented on a suitable amine processing system for plutonium nitrate. Experiments with concentrated plutonium nitrate solutions show that trilaurylamine (TLA) - xylene solvent systems did not form a second organic phase. Experiments are also reported with tri-noctylamine (TnOA)-xylene and TLA-Amsco - octyl alcohol. Two organic phases appear in both these systems at high plutonium nitrate concentrations. Data are tabulated from loading and stripping experiments. (J.R.D.)
Date: January 19, 1961
Creator: Wilson, A. S.
Partner: UNT Libraries Government Documents Department
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Some Heat Transfer Characteristics of ORR Fuel Elements

Description: Analyses are generally made at the ORR with a view toward determining the surface temperatures of fuel plates.
Date: January 19, 1961
Creator: Wett, J. F., Jr.
Partner: UNT Libraries Government Documents Department
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Sources and Availability of Helium

Description: A review of helium sources, availability, consumption, and future production capacity indicates that the helium consumed in the operation of 100 helium-cooled reactors for 300-Mwe power plants over a 20-year period will run no more than a few per cent of the helium consumed in the U. S. in the next 25 years and less than 1% of the helium that is to be stored during that period under the helium conservation act of 1960 (Public Law 86-777).
Date: January 19, 1961
Creator: Fraas, A. P.
Partner: UNT Libraries Government Documents Department
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Spinning of Columbium & Columbium 1%- Zirconium Tubing

Description: The following objectives were planned for this project. (1) Development of spinning data necessary for spinning Columbium and Columbium-1% Zirconium tubing from ingot, forged or welded tube blanks. (2) Determine mechanical & metallurgical properties of spun Columbium and Columbium-1% Zirconium tubing. (3) Determine dimensional and tolerance limits possible to attain on spun Columbium and Columbium-1% Zirconium tubing based on our present equipment, tooling limitations, and the spinning tests p… more
Date: January 19, 1961
Creator: Barker, Wharton R.
Partner: UNT Libraries Government Documents Department
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VARIATIONS IN THE URANIUM-235 CONTENT OF FIFTEEN ORES

Description: The uranium isotope compositions of samples from l5 ores were compared to a standard. Variations of about O.l% of the U/sup 235/ content were observed. (auth)
Date: January 19, 1961
Creator: Smith, L.A.
Partner: UNT Libraries Government Documents Department
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40-tube overbore facility location, C Reactor

Description: Possible locations of the projected 40-tube overbore facility at the C Reactor are discussed from the standpoint of obtaining conversion ratio data applicable to a full-reactor overbore program.
Date: April 19, 1961
Creator: Nilson, R.: Nechodom, W. S.
Partner: UNT Libraries Government Documents Department
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The Attenuation of Natural Environmental Radiation by an Automobile

Description: Report presenting a large number of measurements of natural environmental radiation in various parts of the United States using a 20-liter air filled polyethylene-walled ionization chamber at atmospheric pressure. The ionization current was measured with a vibrating reed electrometer connected as a continuously reading voltmeter driving a pen recorder" (p. 1).
Date: April 19, 1961
Creator: Shambon, Arthur; Lowder, Wayne M. & Solon, Leonard R.
Partner: UNT Libraries Government Documents Department
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Hazards Report for the SM-1 Core II Without Special Components

Description: Abstract: This technical report describes the changes incurred in the SM-1 by the insertion of the SM-1 Core II without special components. The SM-1 Core II components were made to specifications very nearly identical to those of SM-1 Core I. The differences consist of europium absorber sections, internal europium flux suppressors in the control rod fuel elements, and low impurity cladding. Each of the SM-1 Core II components with the exception of the five absorber sections new in SM-1 Core … more
Date: April 19, 1961
Creator: Gallagher, J. G.
Partner: UNT Libraries Government Documents Department
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MSRE Preliminary Physics Report

Description: This report is a compilation of the results of reactor physics calculations to date for the currently proposed Molten Salt Reactor Experiment (MSRE) core design. Estimates have been made of the reactor characteristics using the core model and calculation methods discussed in Reactor Model and Calculation Methods; these results are presented in Table 1 and discussed in Results. Consideration is given to the problems of fission product buildup, fuel salt and Xe-135 retention by the core graphite… more
Date: April 19, 1961
Creator: Nestor, C.W., Jr.
Partner: UNT Libraries Government Documents Department
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On the Activities in the Plant Off-Gas

Description: Measurements were made of the activities in the Laboratory off-gas and efficiencies of the gas cleaning facility were calculated. Sampling was done isokinetically and, by the use of filter paper and charcoal traps, particulates and adsorbable gases were collected.
Date: April 19, 1961
Creator: Fujii, S.; Manneschmidt, J.F.; Mackey, T.S. & Woodall, E.W.
Partner: UNT Libraries Government Documents Department
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Processing data for NIE and NIN KER Loop charges (PT 377)

Description: The following data represents processing conditions used in fabricating prototypic (except for supports) natural and enriched NPR inner fuel elements for Production Test 377. The prototypic NPR inner fuel elements were inserted into zircaloy-sleeves prior to charging. In this way it was possible to simulate, in the KER loops, the conditions under which NPR fuel elements would be subjected under irradiation. The purpose in documenting the data is to provide a permanent record of processing condi… more
Date: April 19, 1961
Creator: Kusler, L. E. & Hays, D. D.
Partner: UNT Libraries Government Documents Department
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Analysis of the stored energy distribution in D-reactor

Description: The purpose of this document is to characterize, as completely as possible, the stored energy distribution in D Reactor as of March 1958, the date of the last stored energy survey and to estimate the temperature rises which can be expected to occur during a stored energy release. D Reactor was chosen for this study only because it represents one of the oldest operating Hanford reactors and not because of any circumstances peculiar to this reactor. 14 refs., 13 figs.
Date: May 19, 1961
Creator: Morgan, W. C.
Partner: UNT Libraries Government Documents Department
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CORE REMOVAL COOLING SYSTEM-SECTION II. CORE I, SEED I. Test Results T- 641113. Section 2

Description: A test was performed on June 19, 1959 to determine the capacity of the Core Removal Cooling System for removing reactor decay heat under split-flow'' conditions. The system operated satisfactorily during this test; the pumps developed a flow of approximates 73 gpm at a total head of 254 ft water, as compared with their rated capacity of 75 gpm at a total head of 250 ft water. (D.L.C.)
Date: May 19, 1961
Partner: UNT Libraries Government Documents Department
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Research and Development Studies on Waste Storage Process

Description: The basic objectives of this program were the determination of the thermal stability of various fission product oxides and nitrates, and an investigation of the gas phase decomposition of ruthenium tetroxide. To accomplish these objectives, a literature survey was flrst made of available physical and chemical data for the oxides and nitrates of Cs, Sr, Ru, Zr, Nb, and Ce. The data were supplemented by a calculation of thermodynamic functions for RuO/sub 4/ vapor from the experimentally determin… more
Date: May 19, 1961
Creator: Ortner, M. H.; Anderson, C. J. & Campbell, P. F.
Partner: UNT Libraries Government Documents Department
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Research and Development Studies on Waste Storage Process

Description: Report documenting "the determination of the thermal stability of various fission product oxides and nitrates, and an investigation of the gas phase decomposition of ruthenium tetroxide" (p. 4).
Date: May 19, 1961
Creator: Ortner, M. H.; Anderson, C. J. & Campbell, P. F.
Partner: UNT Libraries Government Documents Department
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Safety review of Nuclear Fuel Manufacturing Operations: Fuels Preparation Department

Description: Subsequent to a recent comprehensive review of the safety of Hanford`s reactor operations, a request was received from the Hanford Operations Office for a similar review of manufacturing processes within the 200 and 300 areas. Of particular concern were the non-reactor-oriented nuclear and radiological hazards involved in these operations, as well as the administrative procedures by which they were controlled. This report, which reviews these elements of safety of operations within the Fuels Pr… more
Date: May 19, 1961
Creator: Worlton, D. C.
Partner: UNT Libraries Government Documents Department
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Some Properties of Beryllium Oxide

Description: S>The primary objective of the literature search was to determine the best values for the properties involved in the thermal stress parameter. Comparison of data from various investigators indicates that thermal expansion of beryllia is independent of density. A wide variation was found in the thermal conductivity values of beryllia. Graphs and tables are presented which summarize and compare data from various sources. A bibliography of 53 references for some of the major items of the stress pa… more
Date: May 19, 1961
Creator: Lillie, J.
Partner: UNT Libraries Government Documents Department
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Thermal Expansion of Technical Solids at Low Temperatures: A Compilation From the Literature

Description: Report giving tables of the linear contraction relative to 293 ºK, (L293ºLT)/L293, and the linear expansion coefficient, dL/L293dT, of thirty elements, forty-five alloys, twenty-two other inorganic substances and twenty plastics and elastomers in the temperature range, 0 to 300 ºK.
Date: May 19, 1961
Creator: Corruccini, Robert J. & Gniewek, John J.
Partner: UNT Libraries Government Documents Department
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Thermal Stability of Gadolinum Nitrate Solution at High Temperature

Description: During a feasibility study of auxiliary shutdown systems for the Spert II and Spert III reactor facilities, salts possessing high neutron absorption cross sections were considered for use in water soluble poison injection systems, and gadolinium nitrate appeared promising. Tests were carried out in a high pressure static autoclave to determine the stability of gadolinium nitrate solution at elevated temperature. At temperatures of 300 deg F and above, the solution decomposed with formation of a… more
Date: May 19, 1961
Creator: Koenig, J. F.
Partner: UNT Libraries Government Documents Department
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CORROSION ASSOCIATED WITH FLUORINATION IN THE OAK RIDGE NATIONAL LABORATORY FLUORIDE VOLATILITY PROCESS

Description: : : 9 7 7 8 6 9 : = 7 9 9used during the fluorination of fused-salt fuels and subsequent associated operations in the Oak Ridge National Laboratory (ORNL) Fluoride Volatility Process was evaluated. Corrosive attack is reported as mils per month based on molten salt residence time or mils per hour based on fluorine exposure time. Two fluorinators were used in the VPP to carry out the fluorination reactions. These vessels, Mark I and Mark II, were fabricated into right cylinders, approx 4 1/2 ft … more
Date: June 19, 1961
Creator: Litman, A.P. & Goldman, A.E.
Partner: UNT Libraries Government Documents Department
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Hfir Heat-Transfer Studies of Turbulent Water Flow in Thin Rectangular Channels

Description: In support of the High Flux Isotope Reactor program, experimental determinations were made of friction factors, burnout heat fluxes, and average and local nonboiling heattransfer coefficients for forced-convection flow of water through this aluminum and nickel rectangular channels under the following conditions: heat flux = 0.1 x 10/sup 6/ to 7.4 x 10/sup 6/ Btu/hr - ft/sup 2/, velocity = 10 to 85 fps, Reynolds number = 9,000 to 270,000, pressure = 1 to 39 atmospheres absolute, flow gap = 0.043… more
Date: June 19, 1961
Creator: Gambill, W. R. & Bundy, R. D.
Partner: UNT Libraries Government Documents Department
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An Investigation of Some of the Causes for the Spalling of Impregnated Graphite

Description: The impregnation process of the graphite used for investigations of spalling is described. Polished graphite specimens were examined at room temperature using bright field metallographic techniques. The gas evolution characteristics of impregnated graphite were also determined. Results indicated that the amount of impregnant introduced during the fourth impregnation cycle could be a critical factor in causing spalls in the manufacturing process. The permeability of the impregnated graphite was … more
Date: June 19, 1961
Creator: Kosiba, W. L.; Tully, G. R., Jr. & Turovlin, B.
Partner: UNT Libraries Government Documents Department
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Production test-IP-409-A-FP pilot test of self-supported fuel elements in K size smooth-bore zirconium process tubes

Description: This test authorizes installation of up to ten non-overbore size zirconium smooth-bore process tubes into KW Reactor and continued charging of these tubes with KVNS fuel elements until authorized by other means (Process Standards or PITA) or until this test is terminated. While the test authorizes up to 10 tubes, only two process tubes are immediately available and are all that will be planned for in the initial installation and charging. Goal exposure will be set at 800 MWD/T.
Date: June 19, 1961
Creator: Clinton, M. A. & Curtiss, D. H.
Partner: UNT Libraries Government Documents Department
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Reduction of the amount of dichromate added to reactor cooling water: Interim report, Production Test-IP-321-A

Description: Reduced process water treatment costs and incidental benefits of smaller hexavalent chromium discharge to the Columbia River provided incentives to conduct a half-reactor production test. The sodium dichromate (Na{sub 2} Cr{sub 2} O{sub 7}2H{sub 2}O) concentration in process water supplied to the far side of 105-C was lowered from a nominal value of 1.8 to 1.0 parts per million (ppM). This test was started September 26, 1960 and is still in progress. However, a sufficient amount of data is avai… more
Date: June 19, 1961
Creator: Nesselson, E. J.
Partner: UNT Libraries Government Documents Department
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