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Homogeneous Reactor Project Quarterly Progress Report: February-April 1960

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. It includes descriptions of progress and studies conducted during the report period, with tables, illustrations, and photographs.
Date: August 9, 1960
Creator: Briggs, R. B.; Beall, S. E.; Lyon, R. N.; Bohlmann, E. G.; Ferguson, D. E.; McDuffie, H. F. et al.
Partner: UNT Libraries Government Documents Department
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Status and Future Program of Homogeneous Reactor Fuel Processing Studies

Description: The behavior of insoluble corrosion products in the HRT is generally understood and studies of the removal of these solids by hydroclones can logically be terminated after the effect of higher processing rates by the multiple hydroclone has been determined. Chemical descaling may be required to supplement solids removal by hydroclones. Laboratory studies to find suitable reagents will be continued in conjunction with decontamination work presently in progress.
Date: June 17, 1959
Creator: Burch, W. D.; Haas, P. A. & McNees, R. A.
Partner: UNT Libraries Government Documents Department
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Hexone Extraction-Coulometric Titration of Uranium

Description: Samples containing 5 to 10 mg of uranium were extracted with hexone (methyl isobutyl ketone) and titrated coulometrically in sulphate media. Relative standard deviations of 0.45% for samples containing 5 mg and 0.56% for 10 mg were determined by precision studies.
Date: June 22, 1959
Creator: Blevins, E. L.
Partner: UNT Libraries Government Documents Department
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Fuel Cycle Cost for Aqueous Homogeneous Reactors

Description: By using a large central fuel and blanket reprocessing facility, slurry-fueled aqueous homogeneous reactors can attain an estimated minimum fuel cycle cost of 1.4-1.6 mills/kwh; with solution-fueled two-region reactors, a doubling time of 14 years may be obtained at a fuel cycle cost of 2.0 mills/kwh. On-site processing appears desirable only for large power stations made up of reactors designed for short doubling times. For instance, a solution-fueled two-region reactor can attain a 12-year do… more
Date: June 2, 1959
Creator: Culler, F. L.
Partner: UNT Libraries Government Documents Department
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Internally Cooled Molten-Salt Reactors

Description: The initial and long-term nuclear characteristics of two internally cooled heterogeneous, graphite-moderated, two-region, molten-salt reactors have been studied. These reactors have doubling times of 22.5 years and 27.5 years. Methods of decreasing the doubling times by removing the Pa233 from the core and be increasing the specific power of the reactor are described.
Date: June 22, 1959
Creator: Lackey, M. E.
Partner: UNT Libraries Government Documents Department
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Lecture Notes on Reactor Controls

Description: This course on reactor controls is for the purpose of acquainting the student with some of the elementary considerations involved in setting up a control and safety system for a nuclear reactor. This material is the outgrowth of the notes prepared for the lectures on Reactor Controls given in the Oak Ridge School of Reactor Technologu. The lectures given by T. E. Cole in 1953-1955 are the basis of portions of the subject matter on reactor kinetics. Many suggestions and ideas contributed by E. R… more
Date: June 24, 1959
Creator: Walker, C. S.
Partner: UNT Libraries Government Documents Department
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Summary of HRT Run 14

Description: This report presents a detailed study of HRT Run 14, which was abruptly terminated by the formation of a hole in the Zircaloy-2 core tank. In this run the reactor was operated at high temperature and pressure for ten days from March 25 to April 4, 1958. Nuclear power operation extended from March 29 until April 4, when fuel solution leaked into the heavy-water blanket. The maximum power level attained was 6.4 Mw.
Date: June 8, 1959
Creator: Engel, J. R.; Haubenreich, P. N.; Kolb, J. O. & Richardson, D. M.
Partner: UNT Libraries Government Documents Department
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A Feasibility Report on a Method of Direct Total Body Measurement of Enriched Uranium in Man

Description: In certain phases uranium processing it is poss!ble for operating personnel to acquire internal deposits of uranium. This body burden can be acquired by injection, as in contamination of a wound, by ingestion, of by inhalation. In order to estimate internal exposures, some means of determining the location and extent of these internal deposits is essential.
Date: August 7, 1959
Creator: Sanders, Fred W.
Partner: UNT Libraries Government Documents Department
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Run 300A-B Slurry Run of 300A Pump and Loop

Description: The 300A and loop were operated for 2862 hr with thorium oxide slurry at 1500 psi and 280ºC to determine the effects vane inlet and exit geometries on impeller wear, the wear rate of aluminum oxide bearings in this size pump, and the operating characteristics of the loop. The thoris, a 1600*C-fired oxide, had a mean particle size of approximately 2 u. Average circulating slurry concentration was approximately 450 grams of thorium per kilogram of water and average flow rate was approximately 300… more
Date: July 2, 1959
Creator: Moyers, J. C.
Partner: UNT Libraries Government Documents Department
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PRFR Pilot Leaching Plant - Preliminary Process Design

Description: The preliminary process design of a PRFR pilot leaching plant, which is proposed to be located in Cell B of Building ORNL, is considered. Chemical, physical, and nuclear parameters are investigated in order that the leaching operations may be carried out without any chemical or nuclear hazards.
Date: July 23, 1959
Creator: McLain, H. A.
Partner: UNT Libraries Government Documents Department
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Chemical Development Section C Monthly Progress Report July 1959

Description: Nitrate contained in raffinates from Canadian Blind River mills interferes seriously with thorium extraction by secondary amines. With primary amines, however, the effect is negligible and these compounds are the preferred process extractants.
Date: August 5, 1959
Creator: Brown, K. B.; Allen, K. A.; Blake, C. A.; Coleman, C. F.; Crouse, D. J.; Ryon, A. D. et al.
Partner: UNT Libraries Government Documents Department
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A Parametric Study of a Gas Cooled Reactor

Description: The results of a parametric study on a gas cooled reactor are reported on herein. The system considered was a helium cooled, UO2 fueled arrangement with the fuel assemblies consisting of clusters of long cylindrical elements, each element covered b a stainless steel jacket. The axial power distribution was assumed to be a "chopped cosine" having an axial peak-to-average power 1.32.
Date: July 24, 1959
Creator: Epel, L. G.
Partner: UNT Libraries Government Documents Department
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Multiplication Measurements with Highly Enriched Uranium Metal Slabs

Description: A series of neutron multiplication measurements with arrays of 1 by 8 by 10 in. slabs of 93.4% U235-enirched uranium metal have been made to provide data from which safety criteria for the storage of these fissile units can be established. Each slab contained 22.9 kg of U235. A maximum of 125 unites was assembled. The arrays studied were cubic lattices of the units and were usually parallelepipedal in shape.
Date: July 27, 1959
Creator: Mihalczo, J. T. & Lynn, J. J.
Partner: UNT Libraries Government Documents Department
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Investigation of Mechanical Methods of Scale Removal from HRT Heat Exchangers

Description: Tests were conducted to determine methods of removing scale deposits from the HRT heat exchangers. A mockup of the heat exchanger header was cleared of a deposit of iron rust by reverse flushing at a flow rate below 75 gpm. A tube bundle consisting of 109 1/4in. O.D. x 0.049 in. wall tubes was plugged with rust. Approximately 80% of these tubes were unplugged by using a 70 psi water pressure differential in combination with vibration from a pneumatic rivet gun. No mechanical method was employe… more
Date: July 21, 1959
Creator: Gabbard, C. H.; Eissenberg, D. M.; Moyers, J. C. & Namba, I. K.
Partner: UNT Libraries Government Documents Department
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Determination of Li6 in Aqueous Solution by Neutron Activation Analysis

Description: A method for determining the concentration of Li6 in aqueous solution has been tested using the nuclear reactions Li6 (n,α)H3 and O16 (H3,n)F18. Annihilation 7 radiation of induced 1.87 hour F18 radioactivity was counted with a well-type scintillation counter, and the radioactivity per millimole of lithium was found to be independent of lithium concentration below about 0.2moles/liter. The sensitivity limit for detecting lithium is less than 0.1 micromole (0.0075 micromole Li6).
Date: July 10, 1959
Creator: Winchester, J. W. & Bate, L. C.
Partner: UNT Libraries Government Documents Department
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Time Dependence of the Beam in the 86-Inch Cyclotron

Description: In the preliminary stages of getting up a time-of-flight system for measuring neutron spectra from proton reactions, a study of the time dependence of the beam in the 86Inch Cyclotron was made. This study revealed the expected bunching of the protons to produce a short burst of beam on each cycle of the 13.4 Mc/s accelerating voltage. In addition to the 13.4 Mc/s structure, however, there was a 360 c/sec modulation of the beam pulses and a complicated pattern built upon that.
Date: July 29, 1959
Creator: Goodman, C. D.
Partner: UNT Libraries Government Documents Department
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Determination of Oxygen in Oxide Films by Neutron Activation Analysis

Description: Preliminary experiments have been conducted to evaluate the use of the nuclear reactions Li6 (n,α)H3 and O16(H13,n)F18 to determine the thickness of oxide films on metals. Sheets of thin paper and of aluminum, imbedded in powdered LiF, were irradiated with pile neutrons at a flux of 6 x 10^11 n/cm^2/sec and counted with an end-window proportional counter. A saturation activity of 1.87 hr F18 of 150 dis/min per microgram of oxygen was observed in the paper, but radioactivity due to impurities ma… more
Date: July 15, 1959
Creator: Winchester, J. W.; Meyer, R. E.; Bate, L. C. & Leddicotte, G. W.
Partner: UNT Libraries Government Documents Department
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The Rate of Uranium Sorption by a Strong-Base Anion-Exchange Resin

Description: The rate of uranium sorption by a strong-base anion-exchange resin (Dovex 21K) from a uranyl sulfate solution (U 0.005 M, H2SO4 0.02M, SO4 0.2 M) was studied using a stirred vessel technique and measuring the U235 gamma radiation on each bead. Resin initially in the chloride form and the sulfate for was studied.
Date: July 8, 1959
Creator: Bresee, J. C.
Partner: UNT Libraries Government Documents Department
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Spectrophotometric Determination of Microgram Quantities of Osmium With Diphenylcarbazide by G. Goldstein

Description: A method was developed for the spectrophotometric determination of 30 to 100 ug of osmium as OSO4 is extracted with CHCl3 and diphenylcarbazide is then added to the organic extract. A blue-violet reaction product is formed, the absorbancy of which is measured at 560 mu. A suitable reagent concentration is from 3 to 5 ml of 0.2% diphenylcarbazide in a volume of 25 ml and the preferred solvent for the reagent is ethanol. Beer's law is followed over a range of 8 to 130 ug of osmium with a coeffic… more
Date: June 2, 1959
Creator: Menis, Oscar
Partner: UNT Libraries Government Documents Department
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Test of Heater and Cooler Concepts for OCR-ORR Loop, Design 4

Description: High heat flux electrical cartridge heaters were tested with direct air cooling under simulated ORR Loop conditions. The cartridges and the heater design were found to be satisfactory. A gas cooled of concentric pipe design utilizing air, water, and air-water mixtures as the coolant was also evaluated and found to be satisfactory.
Date: July 13, 1959
Creator: Kelley, W. H., Jr. & Storto, E.
Partner: UNT Libraries Government Documents Department
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Zirconium Diboride, Boron Nitride, And Boron Carbide Compatibility with Austenitic Stainless Steel

Description: The compatibility of zirconium diboride, boron carbide, and boron nitride with type 304 stainless steel was evaluated as a function of temperature (1000-1200°C), time (1-3 hr). Appropriate loadings of the boron compounds and stainless steel powder were blended and fashioned into a compact powder metallurgically. Each compact was roll clad into a plate and subsequently heat treated at a temperature equal to the initial sintering temperature. Metallographic examination of the fabricated and heat-… more
Date: July 31, 1959
Creator: Cherubini, Julian H. & Leitten, C. F., Jr.
Partner: UNT Libraries Government Documents Department
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Eurochemic Assistance Program: Comments by FMPC, dated July 6, 1959, on Eurochemic Technical Documents

Description: The nuclear safety portion of this report is inclined to ignore the factors by which safety limits can be increased. It makes no mention of the control that can be exercised by limiting the assay of the U-235 being processed in the plant. From some of the previous reports, it is apparent that this plant is not anticipating processing U-235 of assay greater than approximately 20%. At this value, many of the numbers that are presented in the tables could be increased markedly. Rough examination i… more
Date: July 14, 1959
Creator: Cuthbert, F. L.
Partner: UNT Libraries Government Documents Department
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