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Metallurgy Division Quarterly Progress Report for Period Ending October 31, 1950

Description: Technical report outlining the rate of production of modified MTR type fuel elements for the Bulk Shielding Facility has proceeded. Includes compatibility test that were started as a guide in the selection of materials suitable for fuel-element fabrication. [From Summary]
Date: February 8, 1951
Creator: Frye, J. H.; Miller, E. C. & Bridges, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Corrosion of Various Stainless Steels in Synthetic Waste Solutions

Description: Technical report describing the tests on types 309, 316, and 347 stainless steel. These steels were tested for a total of 779 to 828 hours in three different synthetic waste solutions. Results shoe that the best all-around corrosion resistance to the test conditions was exhibited by 316 stainless steel, but in one solution 347 stainless steel was more resistant. [From Abstract]
Date: February 12, 1951
Creator: English, James L.
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, 1950

Description: Technical report detailing expansion of the Aircraft Nuclear Propulsion at the Oak Ridge National Laboratory. Major facilities completed at this time were the Shielding Rector, the ANP Critical Facility, and the 86-in. Cyclotron. Outlines further need for radiation damage studies. [From Summary]
Date: February 27, 1951
Creator: Briant, R. C.; Ellis, C. B. & Cottrell, W. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Progress Report for Period Ending July 31, 1951

Description: Technical report outlining the effect of strain rate on the tensile properties of thorium. It has been found that the yield strength increases slightly with increasing strain rate, and that tensile strength increases but to a less extent. Studies on the fabrication of thorium by extrusion and drawing have continued, as have studies on the extrusion cladding of thorium and uranium with zirconium. [From Summary}
Date: February 6, 1952
Creator: Miller, E. C. & Bridges, W. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemistry Division Quarterly Progress Report for Period Ending June 30, 1951

Description: Quarterly technical report including reports on chemistry of source, fissionable, and structural elements, nuclear chemistry, radio-organic chemistry, chemistry of separations processes, chemical physics, radiation chemistry, and instrumentation of the Chemistry Division of the Oak Ridge National Laboratory (ORNL). [From Abstract]
Date: February 14, 1952
Creator: Lind, S. C.; Boyd, G. E. & Bredig, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analytical Chemistry Division Quarterly Progress Report for Period Ending September 10, 1951

Description: Technical report covering experiments happening on the Analytical Chemistry Division's sites at the Oak Ridge National Laboratory. Includes information on ionic analyses, radio-chemical analyses, spectrochemical analyses, service analyses, inorganic preparations, analytical chemical control of homogeneous reactor solution, optical and electron microscopy, and service analyses for the period ending September 10, 1951. Studies and happenings took place on the Analytical Chemistry Division's X-10 … more
Date: February 26, 1952
Creator: Kelley, M. T. & Susano, C. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Dynamics of the Supercritical Water Reactor

Description: From introduction: "The work described in this report was carried out as part of the feasibility study (ORNL-117) of a supercritical water reactor (SCWR) for use in nuclear propulsion of aircraft. The object of this work was to study the dynamic behavior of a particular design of supercritical water reactor. Numerical results are presented in Appendix I."
Date: February 1, 1953
Creator: Goertzel, Gerald, 1919-; Shapiro, Mathew M. & Soodak, Harry
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Low Cost Experimental Neutron Chain Reactor Part 2

Description: Description of cooling, shielding, controls are discussed for 100 kw and 1 Mw operation of a low cost experimental neutron chain reactor.
Date: February 5, 1954
Creator: Abernathy, Fred H.; Barrett, Lawrence G.; Berger, William A.; Dever, John A.; Maurer, John F.; Mesler, Russell B. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Stable Isotope Research and Production Division Semiannual Progress Report

Description: The Spectroscopy Research Laboratory is concerned with research and development in the fields of nuclear magnetic resonance, microwaves, infrared and optical spectroscopy, spectrochemistry, and x rays. Research is directed toward fruitful methods of isotope analysis; new element and compound analytical methods having application to immediate Laboratory or long-range commission needs; and fundamental research on isotopes, elements, and compounds. The work is reported on a project basis to give a… more
Date: February 18, 1955
Creator: Keim, C. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Monte Carlo Estimation of the High Energy Neutron Flux Distribution in the ORNL Graphite Reactor

Description: The flux through a given region is proportional to the total lengths of the neutron flight paths that intersect that region. The analytical Monte Carlo procedure manufactured neutron flight paths and totaled the lengths of all paths intercepted by the regions illustrated in Figure 1. The procedure was designed to utilize the various symmetries in the lattice. / Consider a portion of the lattice whose planar cross-section is shown in Figure 5. If R is the region in which the flux is to be estima… more
Date: February 23, 1955
Creator: Moshman, Jack
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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: 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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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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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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The Technology of Uranium Dioxide a Reactor Material

Description: Consideration has been given to various forms of fissionable material for use in atomic reactors, including the pure metals, their alloys and compounds. Of particular interest is the dioxide of uranium which is refractory and corrosion resistant in some environments.The oxide is useful in both granular and bulk forms. Small grains of uranium oxide can be mixed with other materials to form matrix type elements where they serve either as a convenient or necessary form of fuel or fertile material.… more
Date: February 21, 1956
Creator: Johnson, J. R.; Doney, L. M.; Fulkerson, S. D.; Taylor, A. J.; Warde, J. M. & White, G. D.
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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Determination of Trivalent Uranium in Fluoride Salt Mixtures by the Modified Hydrogen Evolution Method

Description: The hydrogen evolution method for the determination of uranium trifluoride which was developed by Manning, Miller and Rowan has been used for the determination of trivalent uranium in this laboratory for the past three years. The method has been applied to many different sample types supposedly pure UF3, mixtures of UF3 and UF4 and the large variety of mixtures of fluoride salts that have been investigated as possible nuclear fuels. These mixtures contained alkali metal, beryllium and zirconium… more
Date: February 26, 1956
Creator: White, J. C.; Meyer, A. S., Jr.; Vaughan, W. F.; Ross, W. J. & Manning, D. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Estimate of the Cost of Production of 10% Isotopic Purity Oxygen-17 by Chemical Exchange

Description: An order of magnitude estimate was made to determine a minimum cost for 10% pure oxygen-17 when produced by a chemical exchange process. the calculations were based on separations factors of 1.03, 1.01, and 1.003. the cost of product was found to vary from $23 per gram for the large factor to $165 per gram for the smaller.
Date: February 1, 1957
Creator: Klima, B. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of HRT Core Sample Holder Upon Core Flow Pattern and Pressure Drop

Description: The measured pressure drop across the reactor core, with the sample holder in place, is 6.9 psi, more than twice the estimated value. Better estimates, based on more rigorous mathematical analysis, should be possible for future problems of this type. The 2% density difference which produced the relatively high velocity of approximately 1 fps, in this experiment, will result from a temperature difference of about 8 C. It is concluded that the bulk fluid temperature near the sample holder will be… more
Date: February 4, 1957
Creator: Hannaford, B. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Bellows Failure in Solids Separation Loop of the HRT Mockup

Description: The failure of the valve bellows would appear to be due to a combination of stress corrosion and crevice corrosion. Stress corrosion occurred as evidenced by the transgranular branched cracking found in the bellows and in the base which which was joined to the bellows. It seems probable that chlorides were present, which, along with the residual stresses present in the bellows assembly, created the necessary conditions for stress corrosion to occur. Crevice corrosion occurred probably due to he… more
Date: February 5, 1957
Creator: Kegler, T. M., Jr. & Hammond, J. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Inert Atmospheres in Non-Vacuum Chambers for Welding Applications

Description: In the HRP Welding program, a major part of the welding and fabrication, and some of the testing, is performed using an inert atmosphere. the use of the inert gas consumable arc welding process and dry box welding or other work in a dry box comes within this category. Since much of the work in the project make use of, or requires, inert atmospheres, a general discussion follows of the methods used, description of equipment, processes, quality of atmospheres, purity requirements, kinetics of met… more
Date: February 6, 1957
Creator: Leonard, W. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of Pressure Differentials on Deflection of the Outer Fuel Plates of Brazed APPR Fuel Elements

Description: One of the considerations in designing a flat plate fuel element is the resistance of the fuel plates, especially the outer plates in the fuel plate array, to deflection and permanent deformation as a result of pressure differentials. An investigation was recently initiated wit the objective of obtaining preliminary information on the APPR-type fuel element to determine the effect of pressure differentials on the outer plates in the fuel assembly. The APPR-1 fuel element consists of 18 flat com… more
Date: February 7, 1957
Creator: Erwin, J. H. & Beaver, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Metallographic Examination of ORNL #1, SHE #2

Description: Small Heat Exchanger ORNL #1, type SHE #2, was removed form test stand B after 2071 hours of operation. Thirty-five samples were removed form the entire heat exchanger. The corrosion found on the outside of the tubes exposed to the fluoride mixture ranged to a maximum depth of .004 inches; however, the frequency of occurrence along the tube wall was heavier at the NaK outlet header, which was the hottest area in the heat exchanger. The depth of attack observed on the fluoride side of this heat … more
Date: February 7, 1957
Creator: VanCleve, J. E.; DeVan, J. H. & Crouse, R. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Extraction of Metal Ions with Di-2-Ethylhexyl Phosphoric Acid

Description: Blake and his co-workers have shown that uranium and other elements can be extracted from acid solutions by various type of organo-phosphorous compounds. Early investigations in the laboratory have demonstrated the applicability of tri-n-alkyl phosphine oxides to the extraction of metal ions from acidic solutions for analytical purposes. This paper is concerned with a similar qualitative investigation of the extraction of metal ions with a di-alkyl phosphoric acid, di-2-ethylhexyl phosphoric ac… more
Date: February 8, 1957
Creator: Ross, W. J. & White, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Costs in Batch- and Continually-Processed Homogeneous Reactors

Description: The fuel requirement of a heavy-water moderated, homogenous, power reactor were estimated for a variety of initial loadings, for both bath and continuous methods of fuel removal. This study considered a 12-ft spherical reactor, temperature 250 C, 500 Mw thermal power, 125 Mw electrical power capability, 0.8 load factor, and 4%/year inventory charges for U and D2O. The fuel shipping-and-processing charges were assumed to be $1/gm of fissionable fuel for the "batch" processed reactors, and $0.37/… more
Date: February 8, 1957
Creator: Kasten, Paul R. & Aven, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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