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Enthalpies and Heat Capacities of Solid and Molten Fluoride Mixtures

Description: The enthalpies and heat capacities of seventeen fluoride mixtures in the liquid state have been determined using Bunsen Ice Calorimeters and copper block calorimeters. The fluoride mixtures were composed of the fluorides of two or more of the following metals: lithium, sodium, potassium, beryllium, zirconium, and uranium. The enthalpies and heat capacities of most of these mixtures were studied in the solid state also. Estimates of the heat of fusion have been made. General empirical equations … more
Date: January 11, 1956
Creator: Powers, W. D. & Blalock, G. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Laboratory Development of the Thorex Process

Description: Changes made in the Thorex process flowsheet were a decrease in the extraction column acidity to decrease thorium losses and the addition of a second thorium solvent-extraction cycle to provide the increased decontamination required when thorium irradiated to 2000-4000 g of U233 per ton is processed. Bonded slugs could not be dissolved by the Thorex flowsheet procedure. Various laboratory scale studies on feed preparation, first-cycle variables, and radiation damage to the solvent are reported.
Date: June 12, 1956
Creator: Wischow, R. P. & Mansfield, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Separation of Isotopes Section Semiannual Progress Report for Period Ending June 30, 1955

Description: The countercurrent gas-liquid system BF3(g)—anisole·BF3(l) for the concentration of boron isotopes has been studied. The single-storage separation factor varies from 1.039 at 0°C to 1.029 at 30°C. Rate of exchange is rapid, and, with efficient contacting equipment, complete exchange may be obtained in less than 15 sec. A total separation of 1.525 has been realized in laboratory equipment. The critical-product reflux reaction is quite efficient. Only about 55 moles of BF3 remain in each million … more
Date: February 23, 1956
Creator: Clewett, G. H. & Drury, J. S.
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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Development of a Cubic Oxide Protective Film on Zirconium

Description: Observations of the effects of neutron damage to zirconium oxides led to the conclusion that the cubic form of ZrO2 is more stable to such damage than the monoclinic form. It has been reported that zirconium corrodes more rapidly in certain liquids when exposure is made under radiation (neutrons and fission products). It is well known that on heating monoclinic ZrO2 a transformation, monoclinic to tetragonal (very similar to cubic), occurs at about 1500°C. The transformation involves sufficient… more
Date: February 21, 1956
Creator: Johnson, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Bibliography of ORNL-BSF Reports Pertinent to Swimming Pool Type Reactor Design (Revised)

Description: Much of the shielding work carried out with the Bulk Shielding Reactor (BSR) has yielded data of particular interest for the design of swimming pool type reactors, However, it is often difficult for a reactor designer to locate such data since it may be recorded in a report primarily concerned with shielding problems. Therefore, this memorandum presents a bibliography of reports from the Bulk Shielding Facility arranged according to the application of data to the various aspects of reactor desi… more
Date: April 13, 1956
Creator: Maienschein, F. C. & Johnson, E. B.
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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HRP Radiation Corrosion Studies

Description: A fifth in-pile loop experiment, L-4-8, was completed. The loop operated in-pile for a total of 1637 hr, during which time the LITR energy output was 4377 Mwhr. The average fission power in the loop based o cesium analyses was 622 w when the LITR was at full power (3 Mw). Based on oxygen data, the generalized corrosion rate for the first 300 hr was 4.0 mpy; the rate for the remaining 1357 hr was 0.7 mpy. The nickel data gave parallel results. The corrosion of the type 347 stainless steel, Zirca… more
Date: August 21, 1956
Creator: Baker, J. E.; Bradley, N. C.; Jenks, G. H.; Olsen, A. R.; Savage, H. C. & Walter, F. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemistry Division Semiannual Progress Report for Period Ending December 20, 1955

Description: Semiannual Progress report of the Oak Ridge National Laboratory Chemistry Division providing updates on various projects, experiments, and other work in inorganic and physical chemistry, nuclear chemistry, organic chemistry, chemical physics, chemistry of separation processes, radiation chemistry, and reactor chemistry.
Date: April 13, 1956
Creator: Taylor, E. H. & Bredig, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Biology Division Semiannual Progress Report for Period Ending February 15, 1956

Description: Progress report of the Oak Ridge National Laboratory Biology Division providing updates on various projects, experiments, and other work. This report includes a summary of scholarly output from the division and departmental activities in cytology and genetics, mammalian genetics and development, microbial protection and recovery, mammalian recovery, pathology and physiology, general physiology, biochemistry, enzymology and photosynthesis, microbiology, plant biochemistry, and biophysics.
Date: April 20, 1956
Creator: Hollaender, Alexander & Carson, Stanley F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analytical Chemistry Division Semiannual Progress Report for Period Ending April 20, 1954

Description: Progress report of the Oak Ridge National Laboratory Analytical Chemistry Division providing updates on various projects, experiments, and other work in ionic analyses, analytical instrumentation, radiochemical analyses, activation analyses, spectrochemical analyses, inorganic preparations, optical and electron microscopy.
Date: July 5, 1956
Creator: Kelley, M. T.; Susano, C. D. & Raaen, H. P.
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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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1956 [Declassified Version]

Description: Progress report of the Oak Ridge National Laboratory Aircraft Nuclear Propulsion Project providing updates on various projects, experiments, and other work. This report includes summaries of project activities in: aircraft reactor test design, ART physics, ART instruments and controls, component development and testing, procurement and construction, ART, ETU, and in-pile loop operations, phase equilibrium studies, chemical reactions in molten salts, physical properties of molten materials, prod… more
Date: September 4, 1956
Creator: Jordan, W. H.; Cramer, 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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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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A Physical Property Summary for Fluoride Mixtures

Description: This report presents a summary of certain physical properties that have been determined experimentally on the fluoride mixture that have been formulated at ORNL (Rers. 1, 2). These properties include the density, enthalpy, heat capacity, heat of fusion, thermal conductivity, viscosity, Prandtl number, electrical conductivity and surface tension. In addition to the experimental data, values have been predicted for the heat capacity and density of the other mixtures from the correlations of these… more
Date: September 5, 1956
Creator: Cohen, S. I.; Povers, W. D. & Greene, N. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Isolation and Purification of Americium

Description: Gram amounts of americium were separated quantitatively from kilogram quantities of lanthanum to yield an americium product approaching 90% purity. The remaining impurity was chiefly yttrium. Elution of americium from 25% loaded Dowex 50 resin column with 0.15 M citric acid— 0.10 M diammonium citrate — 0.3 M ammonium nitrate, pH 3.3 gave a product containing 99% of the americium with a La/Am ratio of 1/100 or less in one fourth of a column volume, in this case about 1 100-fold volume reduction.… more
Date: April 17, 1956
Creator: Campbell, D. O.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Products Produced in Continuous Neuron Irradiation of Thorium

Description: Calculated data and graphs describing the effects of continuous thermal-neutron irradiation of thorium, the usual method of operations of homogeneous reactors, are presented.The buildup and decay of U^233, Pa^233, other heavy isotopes, and fission products are considered on the basis of best available cross-section and fission-yield data. The effects of the heavy isotopes and fission products on neutron economy are discussed.
Date: February 16, 1956
Creator: Gresky, A. T. & Arnold, E. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Solid State Division Semiannual Progress Report for Period Ending August 30, 1956

Description: Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Solid State Division during 1956. Descriptions of progress and studies made are presented. This report includes tables, illustrations, and photographs.
Date: December 17, 1956
Creator: Billington, D. S. & Crawford, J. H., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Closed-Loop Level Indicator for Corrosive Liquids Operating at High Temperatures

Description: Report issued by the Oak Ridge National Laboratory discussing the development of a closed-loop control system. As stated in the statement, "the purpose of this thesis was to design and build a closed-loop control system to be used as an indicator of the level of high temperature liquids contained in a tank" (p. 1). This report includes tables, illustrations, and photographs.
Date: June 4, 1956
Creator: Southern, A. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Enthalpies and Heat Capacities of Solid and Molten Fluoride Mixtures

Description: The enthalpies and heat capacities of seventeen fluoride mixtures in the liquid state have been determined using Bunsen Ice Calorimeters and copper block calorimeters. The fluoride mixtures were composed of the fluorides of two or more of the following metals: lithium, sodium, potassium, beryllium, zirconium, and uranium. The enthalpies and heat capacities of most of these mixtures were studied in the solid state also. Estimates of the heat of fusion have been made. General empirical equations … more
Date: February 1, 1956
Creator: Powers, W. D. & Blalock, G. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of the Excer Process

Description: Two revised Excer process flowsheets are presented for the production of UF4 from urnayl nitrate solution. In both, the uranium is sorbed on a cation-exchange resin and eluted with aqueous HF. In one, the resulting UO2F2 in dilute HF is mixed with dilute sulfuric or hydrochloric acid and electrolytically reduced in a cation-exchange-membrane cell, and the precipitated UF4·0.75H2O is dried and dehydrated to anhydrous UF4. A cost of 20¢ per pound of reduced uranium is estimated. In the other, amm… more
Date: April 17, 1956
Creator: Marinsky, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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