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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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The Radiochemistry of Arsenic

Description: Properties of the element arsenic which would be of value to the radio chemist are annotated. Procedures for radio activation analysis of arsenic were studied and evaluated. These procedures are appended to this memorandum. General criticisms of present methods are presented and a general procedure for the radio activation analysis of arsenic is suggested.
Date: September 3, 1959
Creator: Beard, Harold C.
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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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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Unit Operations Section Monthly Progress Report December 1959 - Chemical Technology Division

Description: Progress is reported on several projects: Druhm, fission product recovery by solvent extraction, fuel cycle development, OCR coolant purification studies, ion exchange, power reactor fuel processing and waste processing.
Date: March 3, 1960
Creator: Bresee, J. C.; Blomeke, J. O.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Watson, C. D. et al.
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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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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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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Plutonium Behavior in the Fluoride Volatility Process

Description: Behavior of plutonium in the Volatility Process as investigated. Both a literature survey and pilot plant experimental work were performed. Additions of 10 mg, 1 g, and 10 g of plutonium were made to the feed salt in three regularly scheduled runs. Although previous experimenters indicated some volatilization of PuF6 would occur, >99 percent of the plutonium remained in the salt in the fluorinator. Maximum product contamination was 3 ppb.
Date: September 3, 1959
Creator: Cross, R. A. & Whitmarsh, C. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Section 9.0 to Status Report on the Disposal of Radioactive Wastes

Description: Section 9.0 is the "Chemical Processes for Fission Product Concentration, Removal or Fixation" section of the Status Report on the Disposal of Radioactive Wastes. The report is divided into four areas: (1) Introduction; (2) Summary of waste processes; (3) Concept of a multipurpose waste processing facility; and (4) Details of some of the waste processes.
Date: September 3, 1957
Creator: Culler, Floyd L., Jr.
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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Radiation Level in the Stator Region of the HRT Fuel Circulation Pump

Description: The gamma dose rate in the motor region of the HRT fuel circulation pump was measured with the pump scroll full of radioactive solution. Extrapolation of the data to the solution activity expected in the pump under normal operation gives a dose rate well below that which would result in excessive gas production in the stator can within the life of the pump. The above dose rate does not include the effects of fast neutrons from the fuel solution or of the general cell radiation level in the vici… more
Date: July 3, 1957
Creator: Engel, J. 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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Testing of Dump Valve Trim in the Valve Test Loop and the Performance of Dump Valves in the HRT

Description: The Homogeneous Reactor Test requires an emergency valve for rapidly releasing the contents of each the core and blanket high-pressure system to its low-pressure system. This report describes the testing of dump valve trim in the Valve Test Loop and the performance of dump valves in the HRT to date.
Date: August 3, 1959
Creator: Hise, E. C.
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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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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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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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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