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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.
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.
Partner: UNT Libraries Government Documents Department
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Calorimetric Calibration of a Graphite Walled, Cavity-Type Ionization Chamber

Description: Technical report outlining cavity-type ionization chambers with graphite walls that are used to measure heat dissipation in the graphite reflector of the MTR mock-up. Studies the relationship between the ionization occurring in the chamber and the heat generated in the surrounding graphite medium. [From Abstract]
Date: January 23, 1951
Creator: Jenks, G. H.; Breazeale, W. M. & Hairston, J. J.
Partner: UNT Libraries Government Documents Department
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Studies on the Removal of Radioisotopes From Liquid Wastes by Coagulation

Description: Technical report covering work completed on the removal of radioisotopes from water using a calcium phosphate floc as a carrier. This research was performed as part of the Health Physics Waste Disposal Research Section work on the removal of small quantities of radioactivity from large volumes of water. [From Abstract]
Date: January 23, 1951
Creator: Lauderdale, Robert A., Jr.
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.
Partner: UNT Libraries Government Documents Department
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Physics Division Quarterly Progress Report for Period Ending September 20, 1950

Description: Technical report covering experiments to measure the resonance and absorption of neutrons in U238 cylinders. Report also discusses control problems connected to the Bulk Shielding Facility and work on MTR controls.
Date: January 8, 1951
Creator: Sneil, A. H. & Wollan, E. O.
Partner: UNT Libraries Government Documents Department
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Criticality Calculations for Hydrogen Moderated Reactors From Microscopic Data

Description: From abstract: "The probability for a fission neutron to escape fast leakage from bare, hydrogen moderated reactors is calculated by a method utilizing only the microscopic cross section of the materials. These results can be employed to determine the effectiveness of other substances in preventing fast neutron leakage. These calculations are carried out for aluminum and iron."
Date: November 29, 1951
Creator: Shapiro, Mathew; Preiser, Stanley & Young, Gale
Partner: UNT Libraries Government Documents Department
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Surface to Mass Dependence of Effective Resonance Integrals for Uranium 238 Cylinders

Description: Technical report outlining the determination of the effective resonance integral for U238 as a function of the mass ratio for cylinders of 5/8" to 3" diameter. Also gives a linear approximation of the effective resonance integral with infinite shielding in the form of a function. [From Abstract]
Date: March 20, 1951
Creator: Risser, J. R.; Arfken, G. B., Jr.; Cuykendall, T. R.; Stephenson, R. J. & Caldwell, D. O.
Partner: UNT Libraries Government Documents Department
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A Solvent Extraction Method for Neptunium (237) Analysis

Description: Technical report describing a rapid and quantitative radiochemical method for the analysis of neptunium (237). This method is based on the extraction of neptunium (IV) with thenoyl-trifluoracetone in xylene. Neptunium (237) is separated free from other alpha emitters and from non-radioactive interferences, and the method may be readily adapted to remote control. [From Abstract]
Date: July 10, 1951
Creator: Moore, Fletcher L.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division Pilot Plant Section Report for November, 1950- January, 1951

Description: Technical report presenting a summary of the flowsheets, equipment, and progress for the Oak Ridge National Laboratory (ORNL) pilot plant development of the Purex Process and of the ORNL Metal Recovery Program. As of this report, conversion of the Purex pilot plant equipment in Buildings 3019 and 3503 is 90% complete. The building structure for the ORNL Waste Metal Recovery plant had been completed, and 15% of the process equipment had been installed. The first hot runs for this plant were sche… more
Date: March 8, 1951
Creator: Jackson, H. K.
Partner: UNT Libraries Government Documents Department
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Shielding Reactor Corrosion Studies

Description: Technical report outlining the investigation of corrosion on MTR type fuel elements for the Shielding Reactor in filtered water. Report includes two basic types of protection: element pretreatment by either anodizing or alodizing, and solution control using nitric acid to maintain a pH of 5.5 to 6.5 or the addition of 60 ppm sodium chromate as an inhibitor. [From Abstract]
Date: July 9, 1951
Creator: Olsen, Arnold R.
Partner: UNT Libraries Government Documents Department
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Dry Fluoride Process Status Report

Description: Technical report outlining how uranium hexaflouride was prepared be the direct combination of irradiated uranium metal with elemental fluorine and subsequently decontaminated by adsorption, filtration, and sublimation on a laboratory scale. Report proposes a survey of other methods of preparing UF6 from uranium metal, a study of adsorption techniques for removing plutonium from UF6, and an investigation of fractional distillation for removing the volatile fission product fluorides from UF6. [Fr… more
Date: March 27, 1951
Creator: Leuse, R. E.
Partner: UNT Libraries Government Documents Department
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Boiling Reactors: A Preliminary Investigation

Description: Technical report detailing kinetic equations that have been developed for a boiling-type reactor and inherent reactor stability studies that have been made on the basis of these equations. Presents features of the proposed reactor, comparisons of circulating types, investigations of bubble-rise velocities, effects of transient conditions of vapor mass in steam chest, and bubble time delay functions yield favorable results. [From Abstract]
Date: December 12, 1951
Creator: Stein, J. M. & Kasten, P. R.
Partner: UNT Libraries Government Documents Department
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Thorium and Thorium Alloys Preliminary Corrosion Tests

Description: Technical report investigating the corrosion resistance of thorium and thorium alloys containing from 2 to 6% chromium, columbinium (niobium), titanium, zirconium and titanium-zirconium in distilled water at 95ºC. The true effects of the various alloy additions could not be determined because of the more marked effect of cold working. [From Abstract]
Date: December 19, 1951
Creator: Olsen, Arnold R.
Partner: UNT Libraries Government Documents Department
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The Hydrolysis of Tributyl Phosphate Ad Its Effect on the Purex Process

Description: From abstract: "The rate of hydrolysis of TBP and the effect of the hydrolysis products in the Purex Process have been studied. Hydrolytic conditions may be encountered in the process which would lead to formation of dibutyl phosphoric acid, causing significant losses of tetravalent plutonium in stripping. This situation may be easily alleviated by reducing and stripping the plutonium in the trivalent state."
Date: December 13, 1951
Creator: Reilly, V. J. & Lanham, W. B.
Partner: UNT Libraries Government Documents Department
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Enrichment of Uranium 236

Description: From abstract: "Neutron-irradiated uranium was electromagnetically separated to provide enrichment of the isotope of mass 236. The final isotopic abundance of U 236 was determined to be 95% in 1800 milligrams of uranium. Useful by-products of the program were 22 grams of 25% U 236 and 1100 grams of 99.7% U 235. These enriched materials have been made available for use on Atomic Energy Commission projects. Possible application of this separation process to recovery of the fuel from the MTR react… more
Date: December 1951
Creator: Harmatz, B.; McCurdy, H. C.; Case, F. N. & Livingston, R. S.
Partner: UNT Libraries Government Documents Department
open access

Enrichment of Uranium 236

Description: From abstract: "Neutron-irradiated uranium was electromagnetically separated to provide enrichment of the isotope of mass 236. The final isotopic abundance of U 236 was determined to be 95% in 1800 milligrams of uranium. Useful by-products of the program were 22 grams of 25% U 236 and 1100 grams of 99.7% U 235. These enriched materials have been made available for use on Atomic Energy Commission projects. Possible application of this separation process to recovery of the fuel from the MTR react… more
Date: December 1951
Creator: Harmatz, B.; McCurdy, H. C.; Case, F. N. & Livingston, R. S.
Partner: UNT Libraries Government Documents Department
open access

Physics Division Quarterly Progress Report for Period Ending March 20, 1951

Description: Technical report covering classified work of the Critical Experiments Program in the Physics Division for the period December 20, 1950 to March 20, 1951. Report outlines investigations of properties of critical assemblies composed of uranium and various reflectors and moderators, preliminary measurements of the effective energy for fission in the assembly. [From Introduction and Summary]
Date: July 2, 1951
Creator: Bernstein, S.; Snell, A. H. & Wollan, E. O.
Partner: UNT Libraries Government Documents Department
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An Investigation of ThF4 - Fused Salt Solutions for Homogeneous Breeder Reactors

Description: Technical report presenting a consideration of the characteristics of fused salt-ThF4 solutions suitable for use in homogeneous reactors. Presented in tandem with a brief survey of the literature pertaining to such solutions and a summary of the experimental work accomplished. [From Abstract]
Date: June 19, 1951
Creator: Blomeke, J. O. & Johnston, C. P.
Partner: UNT Libraries Government Documents Department
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An Experimental Determination of Fission Product Heating After Shutdown of the Low Intensity Training Reactor

Description: Technical report containing the general arrangement of the Low Intensity Training Reactor and outcomes of experiments that have been performed in the reactor to measure the rate of fission product heat dissipation from the fuel pieces after loss of water. [From Summary, Introduction]
Date: September 25, 1951
Creator: Beall, S. E.
Partner: UNT Libraries Government Documents Department
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Chemistry Division Quarterly Progress Report: Period Ending September 30, 1951

Description: This quarterly progress report discusses topics of research and experimentation at the Oak Ridge National Laboratory, including inorganic chemistry, nuclear chemistry, radio-organic chemistry, chemistry of separations processes, chemical physics, radiation chemistry, chemistry of the solid state, instrumentation, reactor chemistry.
Date: September 30, 1951
Creator: Lind, Samuel C., (Samuel Colville), 1879-1965; Boyd, G. E. & Bredig, M. A.
Partner: UNT Libraries Government Documents Department
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Metallurgy of Thorium and Thorium Alloys Interim Report [for] July 1, 1949 to July 1, 1951

Description: Technical report containing a comprehensive study of the physical metallurgy of thorium and some of its alloys containing additions of Be, Si, Zr, Ti, Al, Nb, Cr, Mn, and Ce. Melting range, fabricating characteristics, and tensile properties were studied. [From Abstract]
Date: December 7, 1951
Creator: Frye, J. H. & Hamby, D. E.
Partner: UNT Libraries Government Documents Department
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Mercury Amalgam Bonding of Uranium and Copper

Description: Technical report summarizing one phase of work done to develop methods of bonding uranium to a metal which is a good conductor of heat. Silver was chosen for contact with uranium because it is easy to plate on uranium and there is no danger of brittle Ag-U compounds being formed at elevated temperatures. [From Abstract]
Date: January 22, 1951
Creator: Glasgow, L. G.
Partner: UNT Libraries Government Documents Department
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The Effect of Fluoride on the Corrosion of Stainless Steel in the Presence of Excess Al+3 Ion

Description: Technical report detailing corrosion tests of Type 347 stainless steel for two weeks in boiling uranyl nitrate, sulfuric acid media, with and without additions of Al+3 and F-1 in a 2:1 mole ratio. The results of these tests show that although the presence of aluminum greatly reduces the deleterious effect of fluoride, the corrosion rates are still three to four times greater than when no fluoride is present. [From Abstract]
Date: March 27, 1951
Creator: Olsen, Arnold R.
Partner: UNT Libraries Government Documents Department
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