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Acid Formation in the Radiolysis of Phosphorus Esters

Description: The radiolytic decomposition of tributyl phosphate has been show by burr to product gases, acids, and polymers. the acids that are formed can limit the usefulness of tributyl phosphate for the processing of radioactive materials. The study of acid formation on radiolysis therefor becomes important to us for the understanding of the mechanism of acid formation, the influence of added materials and the effect of the structure of organo- phosphorous compounds. Samples of purified esters have been … more
Date: April 3, 1957
Creator: Baldwin, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Basic Gamma-Ray Data for ART Heat Deposition Calculations

Description: In order that fairly accurate thermal stress calculations can be made on the ART, it is necessary to have a reasonable picture of the temperature distribution in the reactor. To get the temperature distributions, and to determine cooling requirements in various parts of the reactor, one must know the heat deposition rates due to alpha particles, beta rays, gamma rays, and neutrons in all parts of the reactor. The present report contains only the basic physical data necessary to determine the he… more
Date: October 3, 1956
Creator: Bertini, H. W.; Copenhaver, C. M.; Perry, A. M. & Stevenson, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Calculation of the"Negative Mass" Instability for DCX-1

Description: The threshold for an instability by which space charge accumulates in a ring of ions circulating in a magnetic field with negative radial gradient is calculated for DCX-1. With present low densities, the energy spread necessary to quench the instability, a dew tens of Kev, is of the order of the observed energy spread.
Date: July 3, 1961
Creator: Fowler, T. Kenneth
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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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Chemical Technology Division Monthly Progress Report For Chemical Development Section B - February 1960

Description: Progress is reported on dissolution of Consolidated Edison fuel, Zirflex process for decladding PWR blanket fuel, recovery of uranium and thorium from graphite fuels, solvent extraction studies, corrosion studies, ion exchange, waste treatment.
Date: May 3, 1960
Creator: Blanco, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemistry Division Quarterly Progress Report for Period Ending June 30, 1950

Description: Quarterly progress report discussing topics of research and experimentation at the Oak Ridge National Laboratory, including chemistry of source, fissionable, and structural elements; nuclear chemistry; radio-organic chemistry; chemistry of separation processes; chemical physics; radiation chemistry; and instrumentation.
Date: October 3, 1950
Creator: Swartout, J. A.; Boyd, G. E. & Taylor, E. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comparison Of k∞ Measurements In A Critical Assembly With k∞ Measurements In The Physical Constants Testing Reactor

Description: The infinite medium multiplication factor, k∞, for a homogeneous mixture of 2% U235-enriched UF4 in paraffin, was determined from a series of critical experiments in which known changes in the buckling were made and the resulting stable periods measured. The value determined, using a two-group model for the nonleakage probability, is 1.197 ± 0.015. Within the quoted errors this value is in agreement with an earlier value of k∞=1.216±0.013 for the same material experimentally determined in the P… more
Date: May 3, 1960
Creator: Mihalczo, J. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Cooling Hole Distribution for Reactor Reflectors

Description: In the reflector surrounding the core of a nuclear reactor heat generation occurs. In order to keep the thermal stresses within allowable limits or safe guard the reflector from damage, coolant holes must be distributed as to limit the reflector temperature. Contain in in this memo are a series of plots by while the hole distribution can be obtained for a given set of operations conditions for BeO, Be, graphite and BeO-glass.
Date: September 3, 1952
Creator: Farmer, W. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Device For The Collection Of Fecal Specimens

Description: Certain insoluble radionuclides, when inhaled or ingested, eventually pass through the GI tract and can be detected in the feces. To alleviate the problem of cross-contamination and to gain greater cooperation from the person submitting a fecal specimen, a commode seat adapter with a special plastic bag has been designed and installed at the Oak Ridge National Laboratory medical dispensary.
Date: November 3, 1959
Creator: Stone, G. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Effectiveness of Cupric Ion as a Homogeneous Catalyst in the UO3-HNO3-H2O System for the Recombination of Hydrogen and Oxygen Produced by Radiolytic Decomposition

Description: The effectiveness of cupric ion as a catalyst in a UO3-HNO3-H2O fuel system is shown by experimental data. Comparisons are made of the catalytic activity of cupric ion in the nitrate fuel solution and the presently used sulfate system. Calculations are made, using reasonable assumptions, of the permissible power density in watts per cc at several temperatures.
Date: September 3, 1959
Creator: Kelly, M. J.; Silverman, M. D.; Stone, H. H. & Watson, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Coated Al2O3 and Tungsten Carbide Bearing-Journal Assemblies in Westinghouse 100A Pump (Summary of Runs S-96A and S97)

Description: Preliminary results of tests wit the Westinghouse 100A pump indicate that Al2)3 and tungsten carbide coated bearing-journal assemblies prepared by the Linde process are not promising as substitutes for the graphitar-stellite combination. The front Al2O3 assembly failed at start-up with water and both front and rear tungsten carbide assemblies failed after 121 hours with water at 245 C.
Date: May 3, 1957
Creator: Kitzes, A. S. & McLaughlin, C. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Linear Material and Product Consolidation in the DRUHM Process

Description: Tests were made to evaluate magnesia and graphite as possible liner materials for the DRUHM reaction and to evaluate the effect of temperature on product consolidation and separation. In these tests, graphite held up better than magnesia; however, both were attacked by sodium. Appreciable uranium metal consolidation took place at temperatures greater than 1180'C. The results of a literature survey indicated that the most promising liner materials are magnesia, graphite, and graphite coated with… more
Date: September 3, 1959
Creator: Edwards, D. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HFIR Reactor Vessel Expansion Problems

Description: The attached memo by G. N. Krouse of Sturm-Krouse, Inc. gives results of a preliminary analysis of the deflections of beam holes due to thermal expansion and internal pressure in the vessel. A partial solution of the problem is suggested. Based on preliminary pressure-temperature data the following deflections were derived: Movement of horizontal beam tubes = 0.046 in. Movement of Engineering facility tubes = 0.117 in. Vertical motion of the vessel at the horizontal beam tubes due to thermal ex… more
Date: October 3, 1960
Creator: Gall, W. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Project Quarterly Progress Report: February-April 1957

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress of the Homogeneous Reactor Project. Progress of operations, design, development, and analysis is presented. This report includes tables, illustrations, and photographs.
Date: September 3, 1957
Creator: Briggs, R. B.; Winters, C. E.; Beall, S. E.; Lane, J. A.; Bohlmann, E. G.; Ferguson, D. E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hot Cell Demonstration of the Fused Salt Volatility Process

Description: A series of laboratory scale tests showed that high burnup zirconium-uranium fuel can be successfully decontaminated by the Fused Salt Volatility process. Decontamination factors were of the order of 10<sup>6 to 10<sup>9. The UF6 product contained significant quantities of chemical impurities, and additional study is required on their separation. The general success of this work indicates that the ORNL Volatility Pilot Plant will be able to process successfully spent naval reactor fuel.
Date: June 3, 1960
Creator: Cathers, G. I.; Jolley, Robert L. & Moncrief, Eugene C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HRE-E Replacement Reactor Study No. 2

Description: The results of a second HRE-2 replacement reactor design study are reported in which the mechanical, hydrodynamic, and nuclear aspects are discussed in detail. The reactor design which evolved from this study has a 21-in. dia x 42-in. long cylindrical core (vol = 200 liters) partially reflected by a 4-in. thick beryllium reflector, surrounded by a thorium blanket, and enclosed in a 52.0-in. ID steel pressure vessel. By making the Zircaloy-2 core tank, beryllium reflector, and thoria blanket rem… more
Date: July 3, 1961
Creator: Chapman, R. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HRT Reactor Hazards

Description: Several potential hazards that have been recognized and anticipated in the design and fabrication of the pressure vessel in the Homogeneous Reactor Test are discussed. These hazards results from the high operating pressure and temperature of the reactor, the exposure of the reactor vessel material to potential embrittlement and other affects of fast-neutron irradiation, and the need for containment of corrosive flowing liquids. The steps taken in recognition of these hazards are also discussed.… more
Date: August 3, 1956
Creator: Miller, E. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hydrogen Evolution From Uranium-233 Product Solutions

Description: A graphical method is presented for the calculation of the standard milliliters of hydrogen per hour evolved from solutions of uranium-233. Variation in evolution due to concentration of uranium-233, concentration of uranium-232, and growth of the daughters of uranium-232 with time are included.
Date: March 3, 1960
Creator: Rainey, R. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Methods of Controlling Core-Wall Temperatures in Aqueous Homogeneous Reactors

Description: The problem of controlling the surface temperatures of core vessels in two-region aqueous homogeneous reactors has been examined by analyzing several possible systems for cooling the wall: (1) direction of the inlet core fluid along the wall at a high velocity; (2) passage of heavy water through the wall of a double-wall core vessel; and (3) flow of cool blanket slurry past the wall.
Date: June 3, 1959
Creator: Rosenthal, M. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Observed performance of the Fuel Sample Cooler

Description: Measurements of flow rate through the fuel high-pressure system sampler indicate that the average flow rates is about 0.29 gpm (145 lb/hr) plus or minus 50%, which affords an adequate purge of from 12 to 36 volumes through the sample line if the full fifteen minutes of purging is allowed before isolating the sample. The fuel sample cooler was fund to have adequate capacity to reduce the temperature of the fuel solution form about 275 to 70 C, using pre-heated cooling water at 70 C. Uncertaintie… more
Date: June 3, 1957
Creator: Van Winkle, R. & Wiethaup, R. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Operation of the EGCR Purification System Prototype

Description: Tests were conducted on a small-scale model of the experimental gas-cooled reactor (EGCR) at the Oak Ridge National Laboratory to determine the effectiveness of the system in removing gaseous impurities from circulating helium. Results indicated that hydrogen, carbon monoxide, and methane could be satisfactorily removed by oxidation in a catalytic converter.
Date: April 3, 1961
Creator: MacPherson, R.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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