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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.
Partner: UNT Libraries Government Documents Department
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Anion Exchange Separation Of Trivalent Actinides And Lanthanides

Description: Separation of americium and curium from rare earths by anion exchange based on selective chloride complexing has been developed and tested on a laboratory scale with tracer amounts of Am-241 and Cm-242 and macro amounts of mixed rare earths.
Date: June 3, 1960
Creator: Lloyd, M. H. & Leuze, R. E.
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.
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.
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.
Partner: UNT Libraries Government Documents Department
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Effect of Non-Thermal Capture on Californium Production in the HFIR

Description: The purpose of this study is to estimate the additional production of Cf-252 from non-thermal captures in the present concept of the HFIR and to attempt to establish an optimum ratio of non-thermal to thermal flux.
Date: December 3, 1959
Creator: Claiborne, H. C.
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.
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.
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.
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.
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.
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.
Partner: UNT Libraries Government Documents Department
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Thermal Column Neutron Flux

Description: Relaxation methods are used to calculate the thermal neutron flux distribution for a central plane of a reactor thermal column. The flux distribution for the idealized column used in the calculations is superimposed on a drawing of a proposed thermal column.
Date: September 3, 1947
Creator: Noderer, L. C. & Coveyou, R. R.
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.
Partner: UNT Libraries Government Documents Department
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Xenon Poisoning in Molten Salt Reactors

Description: The xenon poison fraction in a 1000-mwe molten salt breeder reactor power plant (MSBR) was calculated as a function of sparging cycle-time and the rate of diffusion of xenon into graphitic structure in contact with the fuel salt. It was found that the xenon poison fraction can be held to 0.005 neutrons per neutron absorbed in fuel atoms by passing the fuel stream through a helium sparge-chamber at the rate of 10 ft/sup 3//sec if the coefficient of diffusion is no greater than 10(-7) cm2/sec. or… more
Date: May 3, 1961
Creator: Miller, J. W.
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.
Partner: UNT Libraries Government Documents Department
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Progress Report - Pneumatic Temperature Measuring System

Description: This research report details developments in the effort to predict the speed of response of the basic pneumatic probe at the Oak Ridge National Laboratory.
Date: March 3, 1961
Creator: Hochreiter, H.M.
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.
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.
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.
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.
Partner: UNT Libraries Government Documents Department
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