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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.
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.
Partner: UNT Libraries Government Documents Department
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Investigation of Materials for a Water Cooled and Moderated Reactor [Secret Version]

Description: An investigation of the materials for use in the water-moderated and cooled Aray Package Power Reactor (APPR) operating at about 500°F was made. The available literature was analyzed, and the results of the different investigators were compared and averaged. Twenty different materials, including stainless steels, nickel alloys, Stellites and others, were investigated from the point of view of physical properties, susceptibility to radiation damage, and corrosion resistance. Corrosion rates were… more
Date: August 1954
Creator: Scheib, Louis
Partner: UNT Libraries Government Documents Department
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Investigation of Materials for a Water Cooled and Moderated Reactor [Declassified Version]

Description: An investigation of the materials for use in the water-moderated and cooled Aray Package Power Reactor (APPR) operating at about 500°F was made. The available literature was analyzed, and the results of the different investigators were compared and averaged. Twenty different materials, including stainless steels, nickel alloys, Stellites and others, were investigated from the point of view of physical properties, susceptibility to radiation damage, and corrosion resistance. Corrosion rates were… more
Date: August 1954
Creator: Scheib, Louis
Partner: UNT Libraries Government Documents Department
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Analysis of the Combustion of Graphite-Uranium Fuels in a Fixed Bed or Moving Bed

Description: The first step in a proposed processing method for recovery of uranium from graphite-uranium fuels consists of oxidation of the fuel by oxygen to volatilize the carbon. Residue ash from the combustion step can be treated in a variety of ways to recover and purify the uranium. The combustion step may be caried out by contacting the solid fuel in a fixed or moving bed with a stream of oxygen-bearing gas in a tubular or annular reactor. Oxidizing gas may be introduced to the reactor at several poi… more
Date: August 13, 1964
Creator: Scott, Charles D.
Partner: UNT Libraries Government Documents Department
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Graduate Programs for the Health Physicist in the United States

Description: The first man-made nuclear reactor -- or "pile" as it was then called -- was rather hurriedly improvised and operated in a crowded space under the athletic bleachers of Stagg Field at the University of Chicago on December 2, 1942. Just prior to this time, there began the assembly of a group of physicists with an unusual assignment. They were determined that radiation hazards of unprecedented proportions must be coped with successfully in the conduct of reactor programs as planned. Since these p… more
Date: August 13, 1964
Creator: Morgan, K. Z. (Karl Ziegler), 1908-
Partner: UNT Libraries Government Documents Department
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Thermal Properties of Grade CGB Graphite

Description: Grade CGB graphite is a nuclear graphite which is basically an extruded petroleum coke bonded with coal tar pitch. No carbon blacks are used and the low-permeation graphite is finished through a series of impregnations and heat treatments with a final heat treatment of all components to 2800 degrees C. A listing of the results obtained is given in Table 1. The results at 51 degrees C are considered questionable. There was a slight contamination of the 90% Pt 10% Rh-Pt thermocouples at 910 degre… more
Date: August 11, 1964
Creator: Moore, J. P. & Godfrey, T. G.
Partner: UNT Libraries Government Documents Department
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Comparison of the Thermal Conductivity, Electrical Resistivity, and Seebeck Coefficient of a Hight-Purity Iron and Armco Iron to 1000 [degrees] C

Description: The thermophysical properties of Armco iron such as thermal conductivity, electrical resistivity, and Seebeck coefficient have been extensively investigated and reviewed up to 1000 degrees C. Few investigations of such properties have been made on high purity iron. If such a study is made using the same apparatus to determine the properties of two purity levels of iron, then several significant intercomparisons can be made which add meaning to data on a single material. The systemic errors for … more
Date: August 11, 1964
Creator: Moore, J. P.; Fulkerson, W. & McElroy, D. L.
Partner: UNT Libraries Government Documents Department
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A Thermal Comparator Apparatus for Thermal Conductivity Measurements from 50 to 400 [degrees] C

Description: The experimental details, mathematical models, and typical data for a rapid comparative method for thermal conductivity measurements are presented. The method consists of measuring the temperature change of a small silver sphere after it is brought in contact with a small disk-shaped specimen which was initially at ta higher temperature. This temperature change was calibrated in the range of 50 to 400 degrees C by making measurements on samples of know thermal conductivity. The accuracy of this… more
Date: August 11, 1964
Creator: Kollie, T. G.; McElroy, D. L.; Graves, R. S. & Fulkerson, W.
Partner: UNT Libraries Government Documents Department
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Deposition of Submicron-Size Particles in Ventilation Ducts

Description: The purpose of this study was to investigate mathematically the concentration decrease due to particle deposition phenomena in highly concentrated monodispersed aerosols (mean particle size less than 1.0 mu) flowing through ventilation ducts. It was found that, from the standpoint of removal, the decrease in concentration due to deposition on duct walls was insignificant; but, when considering contamination on duct walls, the amount deposited, even though small when compared with the amount in … more
Date: August 1964
Creator: Davis, L. P.
Partner: UNT Libraries Government Documents Department
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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending June 10, 1952

Description: This quarterly progress report details ongoing work at the Oak Ridge National Laboratory as part of the Aircraft Nuclear Propulsion Project. Topics of discussion include reactor theory and design, shielding research, materials research, appendixes with information on ongoing analytical chemical studies.
Date: August 5, 1952
Creator: Briant, R. C.; Buck, J. H.; Miller, A. J. & Cottrell, W. B.
Partner: UNT Libraries Government Documents Department
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Mammalian Radiation Genetics

Description: "This symposium is concerned with the basic aspects of radiation effects. When we turn to the genetic effects of radiation in mammals, there are so few aspects on which there is any information that the problem of sorting out the fundamental findings has hardly arisen. In this paper it will, therefore, be possible to survey most of what is known and pass on to a consideration of what is needed next. Since one of the purposes of this symposium is an interchange of views between investigators in … more
Date: August 11, 1952
Creator: Russell, W. L.
Partner: UNT Libraries Government Documents Department
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Organo-Phosphorous Compounds for Solvent Extraction

Description: From summary: "The influence of the structure of phosphate esters on the distribution coefficient of uranium between solutions of these esters in carbon tetrachloride and aqueous nitrate solutions has been studied. Esters of secondary alcohols showed higher distribution coefficients than primary alcohols. Phenyl esters extracted less uranium than alkyl esters, and the presence of other negative groups also resulted in less extraction. Compounds containing carbon to phosphorus bonds gave higher … more
Date: August 14, 1952
Creator: Higgins, C. E.; Baldwin, W. H. & Ruth, J. M.
Partner: UNT Libraries Government Documents Department
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Protective Equipment Evaluation Program Quarterly Progress Report: July-September 1951

Description: This quarterly progress details the ongoing work of the Protective Equipment Evaluation Program at the Oak Ridge National Laboratory. Topics discussed include aerosol generation, penetration studies, particle size measurement, and an appendix with analytical methods.
Date: August 6, 1952
Creator: Struxness, E. G.
Partner: UNT Libraries Government Documents Department
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Heat Transfer and Pressure Loss in Tube Bundles for High Performance Heat Exchangers and Fuel Elements

Description: From introduction: "The tube arrangement covered in this report was proposed in June, 1950, as a means of halving the weight and volume required for the heat exchanger. Ideally, the pressure drop across this arrangement should be little more than that required to overcome the skin friction on the tube surfaces. If the pressure drop across the tube spacers and in the cross-flow regions can be kept low, this ideal can be approached. much of the test work covered in this report was devoted to this… more
Date: August 12, 1952
Creator: Cohen, G. H.; Fraas, A. P. & LaVerne, M. E.
Partner: UNT Libraries Government Documents Department
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Laboratory Development of the MTR-RaLa Process for the Production of Barium140

Description: From abstract: "This report presents the laboratory development of the MTR-RaLa Process for the production of barium140 from Materials Testing Reactor assemblies." The laboratory studied four possible chemical schemes with the final process being chosen "on the basis of chemical yield and purity of product, ease of recovery of uranium235, simplicty of equipment, and overall time required for processing" (from introduction).
Date: August 19, 1952
Creator: Blanco, R. E., (Raymond Eugene), 1918-1987; Kibbey, A. H.; Pannell, J. H.; Shank, E. M.; Farmer, J. E.; Helton, D. M. et al.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Progress Report for Period Ending January 31, 1952

Description: This quarterly progress report describes the ongoing research at the Metallurgy Division at the Oak Ridge National Laboratory. In particular, this report discusses the thorium research program, the slug problem, the preferred orientation and anisotropy in metals, fundamental studies of alloying, and the ANP program.
Date: August 28, 1952
Creator: Frye, John H., Jr., 1908-2001 & Bridges, W. H.
Partner: UNT Libraries Government Documents Department
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Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: First Quarterly Report, October-December 1961

Description: Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: August 15, 1963
Creator: Leitz, F. J.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Eleventh Quarter, January-March 1962

Description: From introduction: "This is the eleventh of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: August 1962
Creator: Pennington, R. T.
Partner: UNT Libraries Government Documents Department
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In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C

Description: Report presenting in-pile loop experiments DD, EE, FF, GG, L-412, L-413, and L-418, which were seven of a series designed to test the radiation corrosion of zirconium, titanium, and stainless steel alloys in solutions under various conditions of radiation intensity, temperature, solution composition, and velocity of flow. Steel specimens exposed in the loop cores showed increases in corrosive attack over that expected out-of-radiation.
Date: August 15, 1963
Creator: Jenks, G. H. & Baker, J. E.
Partner: UNT Libraries Government Documents Department
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