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Chemical Development Section C Progress Report for October-November 1960

Description: Studies are being made on the recovery of thorium (and uranium) from granitic rock, since this source represents a very large potential thorium reserve for the nuclear power industry. In preliminary leaching studies on 16 granite samples (containing 8-95 ppm thorium and 1.5-16 ppm uranium), maximum recoveries of thorium and uranium ranged 30-85% and 15-65% respectively, and sulfuric acid consumption was high (30-120 lbs H2SO4 per ton of granite). A relatively high acidity was needed to obtain r… more
Date: March 3, 1961
Creator: Brown, K. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Two Group Calculations for Flux Distribution and Critical Mass in Clean Cold ORR Cores

Description: A series of two-group calculations has been made on the Oracle for the purpose of obtaining critical-mass and flux distribution data for various ORR core configurations. The 3G3R code of Bate, Einstein, and Kinney was used, together with the RSP code developed by Nelson. This made it possible to obtain results for the three-dimensional case. The results, which are presented graphically, are intended to serve as a guide for the design of experiments until such time as actual measurements are ava… more
Date: March 11, 1958
Creator: Binford, F. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effects of Heat Treatment on Microstructure and Fabricability of 48 wt % Uranium - 52 wt % Aluminum Alloys

Description: It has been reported in the literature that prolonged soaking of 16 wt & uranium-aluminum alloys at elevated temperatures induces a microstructural changed termed "conglobulation". this process is essentially a spheroidization of the UAl4 eutectic. Conclusions of the tests: (1) Extended soaking of 48 wt $ uranium-aluminum alloy billets at 600 C does not improve their hot-rolling characteristics. (2) Soaking periods of 50 hours and greater reduce the tensile and yield strengths of these alloys.… more
Date: March 15, 1957
Creator: Thurber, William C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiation Dose Received by Passengers and Crew on Planes Carrying the Maximum Number of Radiation Units

Description: The dose of ionizing radiation received by passengers and crew members traveling on commercial airlines which transport radioisotopes is of interest to all persons who travel the airways frequently. Tariff regulations permit the air transport of 40 units of radioactive materials where one unit represents a quantity of radioisotopes which when packaged delivers a dose rate of one mr/hr at a distance of one meter from the center of the package. Using five different types of commercial aircraft, s… more
Date: March 1, 1957
Creator: Davis, D. M.; Hart, J. C. & Warden, A. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Anisotropic Elastic Scattering of Neutrons

Description: In an elastic collision the neutron loses part of its kinetic energy to the nucleus with both the kinetic and momentum of the system being conserved. However, for many elements the scattering is not isotropic in the center-of-mass system at the higher neutron energies. Many of the present reactor multigroup codes include anisotropic scattering at the high neutron energies, while many others assume isotropic scattering at all energies. In order to consider some of the effects of including anisot… more
Date: March 21, 1957
Creator: Copenhaver, C. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Compatibility Tests of Various Materials in Molten Sodium

Description: Several compatibility test of various materials in contact in sodium under 500 psi pressure were conducted for 716 hr at 1500 F. Of the diffusion couples studies, the Inconel-beryllium system showed the largest amount al alloying. The reaction between molybdenum and beryllium resulted in the formation of two compounds, both of which were severely cracked in several areas. The molybdenum-INOR #8, and the INOR #8p type 316 stainless steel interfaces showed little if any alloying.
Date: March 25, 1957
Creator: Carlander, R. & Hoffman, E. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Source of Fission Products in LITR Cooling Water

Description: A study has been made of the radioactive nuclides present in the cooling water of the Low Intensity Test Reactor. Prominent nuclides which have been identified include Np239 and certain fission products. The experimental evidence points to the probability that there could be adequate U235 contamination on the fuel plates to quantitatively account for the fission products identified in the LITR cooling water. inasmuch as new aluminum does not contain uranium, it must be assumed that the contamin… more
Date: March 26, 1957
Creator: Moeller, D. W. (Dade W.) & Leddicotte, G. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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In-Reactor Autoclave Corrosion Studies. II, Autoclave Z18

Description: In order to test the effect of chromate ion on the corrosion of Zircaloy-2, a 0.04 m uranyl sulfate solution (enriched) containing added acid, copper sulfate and 557 ppm of Cr (VI) was autoclaved with rocking at 280 degrees C for about eight days in the HB-5 facility of the LITR. The average corrosion rate established by the rate of consumption of oxygen was 9.9 mpy at a power density of 4.9 w/ml. It is indicated by comparison with a previous corrosion study under LITR radiation that the presen… more
Date: March 22, 1957
Creator: Warren, K. S.; Davis, R. J. & Jenks, G. H. (Glenn Herbert), 1916-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Beryllium

Description: The information concerning beryllium assembled herein has been selected primarily to provide information that might be pertinent to the design of the ART. The creep-rupture data in the literature have been obtained from vacuum cast and extruded beryllium, rather than from the hot-pressed beryllium which will be used in the ART. A research program is being conducted by the Brush Beryllium Company, under contract to the Oak Ridge National Laboratory, which will eventually provide the design engi… more
Date: March 21, 1957
Creator: Whitman, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Measurement of the Friction Characteristics for Flow in the ART Fuel-to-NaK Heat Exchanger

Description: The friction characteristics of a full-scale straight-tube model of the ART fuel-to-NaK heat exchanger were determined experimentally. The presence of the spacers resulted in a transition to semi-turbulent flow at a Reynolds modulus of 350. this semi-turbulent flow persisted up to a Reynolds modulus of 5,000. The circumferential spacers were found to contribute slightly more than the radial spacers to the pressure loss in the heat exchanger.
Date: March 19, 1957
Creator: Cohen, S. I. & Jones, T. N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TBP Stripping in Bubble-Cap Column and Concomitant Product Evaporation

Description: A study was conducted to demonstrate the stripping and evaporation steps in a Purex-type uranium recovery process and to ascertain the operating behavior of the equipment under a range of conditions. The factors considered were control, effectiveness, and reliability of equipment and optimum feed point. Experimental procedures are described, and recommendations for equipment modifications are included. (J.R.D.)
Date: March 18, 1957
Creator: Long, J. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comments on the Determination of the Particle Size Distribution of Thorium Oxide

Description: Factors affecting the results of thoria particle size distribution measurements by sedimentation procedures currently and recently employed are considered. The effects of thoria concentration, solvent, dispersant, thoria properties, and other factors are discussed.
Date: March 31, 1957
Creator: Moore, G. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High-Temperature Properties in Relation to Design

Description: The essential physical and mechanical properties of materials which enter into the design considerations of high-temperature systems have been outlined, and the relationship of these factors to the detailed design of structural members noted. Particular attention is given to the phenomenon of strain-cycling and relaxation, and several engineering devices wherein these effects can markedly influence design are mentioned. Techniques and apparatus for the measurement of strain-cycling and relaxati… more
Date: March 14, 1957
Creator: Weir, J. R.; Meghreblian, Robert V. (Robert Vartan) & Douglas, D. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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In-Pile Slurry Loop Program

Description: The in-plie slurry loop work is now being considered as a joint program between the PAR project and ORNL. It is proposed that PAR design, fabricate and test the in-pile loops and that ORNL operate the loops in-pile, dismantle the loops after irradiation and made the appropriate measurements to determine the radiation effects. This report gives the objects of the slurry in-pile program and outlines the facilities and operations required to execute ORNL's part of this program.
Date: March 8, 1957
Creator: Arehart, T. A.; Compere, E. L. (Edgar L.); Ferguson, D. E.; Korsmeyer, R. B. & McBride, J. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Neutron and Gamma-Ray Attenuation for a Fission Source in Water : Comparison of Theory with LTSF Measurements

Description: Calculations are presented of the fast neutron dose rate, the gamma-ray dose rate, and the thermal neutron flux along the source plate axis in the Lid Tank with the tank filled entirely with water. These calculations are compared with experimental measurements. The calculations are absolute and are compared with absolute measurements.
Date: March 12, 1957
Creator: Otis, David Ridgway
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Volatility Pilot Plant : Design of a NaF Packed Tower for Removing HF from Fluorine

Description: A 4-ft-7-in. adsorption column packed with 1/8 in. sodium fluoride pellets was designed to reduce the hydrogen fluoride content of the fluorine being used by the Volatility Pilot Plant from 5% to less than 0.01%. It will be a non-isothermal packed bed with the bas inlet heated to 100 C to avoid plugging and the exit cooed to 25 C for more complete HF removal.
Date: March 7, 1957
Creator: Watson, J. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Semipermanent Freeze Plug Tests for HRT-CP

Description: Five uninsulated semipermanent freeze coils, series connected, can be frozen when submerged in 70 F water with a Freon-11 flow rate of 1.85 gpm at an inlet temperature of -40 F. The refrigeration unit of the HRT-CP is capable of delivering >3 gpm to a similar semipermanent freeze coil system located in Cell C. Therefore the number of F-11 risers required in Cell C of the HRT-CP can be minimized by series connecting this many semipermanent freeze coils where required.
Date: March 11, 1957
Creator: Winget, R. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Sodium Hydroxide - Sodium Hydride System

Description: Portions of the NaOH-NaH phase diagram were studied by means of differential thermal analysis. Under certain conditions NaH will either react with NaOH according to the equation NaH + NaOH in equilibrium Na/sub 2/O + H/ sub 2/ or thermally dissociate according to the equation NaH in equilibrium Na + 1/2 H/sub 2/. Both of these reactions are suppressed by a high H/sub 2/ pressure; and NaH neither reacts nor dissociates to an extent sufficient to affect the results reported. This was evidenced by… more
Date: March 7, 1957
Creator: Kerzner, Marvin S.; Kelly, Henry C. & Johnson, Sidney
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Sodium Hydroxide - Sodium Oxide - Sodium - Sodium Hydride - Hydrogen System

Description: Sodium hydride dissolves in and reacts with molten NaOH to give an equilibrium mixture of NaH, NaOH, Na/sub 2/O, Na, and H. In the case where there is a gaseous phase (hydrogen) and only one condensed phase, the system is defined by the temperature, pressure, and one composition variable. The equilibrium, H/ sub 2/ pressure, which is a measure of the H/sub 2/ activity within the melt, was determined as a function of the composition of the condensed phase(s) at 600, 700, and 500 deg for equilibr… more
Date: March 7, 1957
Creator: Kelly, Henry C.; Sullivan, Edward A. & Johnson, Sidney
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fission Product Activities in Irradiated Natural Uranium, Enriched Uranium, and Thorium

Description: Calculated data and graphs describing the effects of batch thermal-neutron irradiations on the buildup of fission products in natural uranium, enriched uranium, and thorium are presented together with empirical equations and plots correlating total fission product activities and/or decontamination factors. Fluxes of 1012-1015 are considered.
Date: March 28, 1956
Creator: Arnold, E. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending December 10, 1955

Description: This quarterly progress report of the Aircraft Nuclear Propulsion Project at ORNL records the technical progress of the research on circulating-fuel reactors and other ANP research at the Laboratory under its Contract W-7405-eng-26. The report is divided into three major parts: I. Reactor Theory, Component Development, and Construction, II. Materials Research, and III. Shielding Research. The ANP Project is comprised of about 530 technical and scientific personnel engaged in many phases of rese… more
Date: March 12, 1956
Creator: Jordan, W. H.; Cremer, S. J.; Miller, A. J. & Savelainen, A. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Mathematics Panel Semiannual Progress Report

Description: From July through December, a total of 1750 hr of computer time was used by programmers in "debugging" and in running problems. With the acquisition of a second operator, the evening shift was initiated. A night-shift operator is presently being trained, and third-shifts operations will probably begin after completion of the magnetic-tape memory. / Engineering time is regularly scheduled for 4 hr each morning and 1/2 hr late in the afternoon. An electronic technician is on duty during evening-s… more
Date: March 2, 1955
Creator: Householder, A. S. & Sangren, W. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Joint National Institute for Health-Atomic Energy Commission Zonal Centrifuge Development Program, Semiannual Report for Period July 1 - December 31, 1962

Description: This technical report describes development work done on zonal centrifuge systems at the Oak Ridge National Laboratory and the Oak Ridge Gaseous Diffusion Plant during the period July 1 to December 31, 1962 under the Joint National Institute for Health-Atomic Energy Commission Zonal Centrifuge Development Program. A basic purpose of this project is to develop new methods for isolating virus particles associated with cancerous cells and tissues. Three classes of rotor systems capable of separati… more
Date: March 4, 1963
Creator: Anderson, N. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Effect of Fluoride on the Corrosion of Stainless Steel in the Presence of Excess Al+3 Ion

Description: Technical report detailing corrosion tests of Type 347 stainless steel for two weeks in boiling uranyl nitrate, sulfuric acid media, with and without additions of Al+3 and F-1 in a 2:1 mole ratio. The results of these tests show that although the presence of aluminum greatly reduces the deleterious effect of fluoride, the corrosion rates are still three to four times greater than when no fluoride is present. [From Abstract]
Date: March 27, 1951
Creator: Olsen, Arnold R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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