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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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Analysis of Bulk Shielding Facility Neutron Dosimeter Data

Description: Technical report calculating "effective removal cross sections" for Pb, Fe and O from measurements of fast neutron does in the water surrounding the BSF reactor. The values for Pb and Fe agree quite well with those previously determined from Lid tank data, whereas that for O is somewhat lower. [From Abstract]
Date: July 17, 1952
Creator: Podgor, S.
Partner: UNT Libraries Government Documents Department
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Solution of Experimental Breeder Reactor Slugs

Description: From abstract: "A full-scale, always-safe, metal dissolver for Experimental Breeder Reactor fuel was designed, built, and installed for test operation. It was found that the dissolver operated satisfactorily, and feasible operating procedures were established for the dissolution of bare, or jacketed, EBR slugs. Minor modifications of the dissolver design have been required to accomodate [sic] a modified EBR slug, but it is believed that this will not significantly affect its operating character… more
Date: March 11, 1952
Creator: Sampson, E. M., Jr.
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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Metallurgy Division Quarterly Progress Report: Period Ending October 31, 1951

Description: This quarterly progress report discusses ongoing research and experiments at Oak Ridge National Laboratory in the Metallurgy Division. This report discusses thorium research, the mechanical properties of metals including thorium, uranium, inconel, and z-nickel, the ANP program (including the following topics: the physical chemistry of liquid metals, and welding research), and the materials testing reactor program.
Date: April 21, 1952
Creator: Frye, John H., Jr., 1908-2001 & Bridges, W. H.
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
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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
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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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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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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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Aircraft Nuclear Propulsion Project Quarterly Progress Report: Period Ending September 10, 1951

Description: The first part of this quarterly progress report details reactor theory and design, discussing the aircraft reactor experiment, experimental reactor engineering, reactor physics, and critical experiments. The second part of this report is not included. The third part of this quarterly progress report details materials research, discussing corrosion research, physical properties and heat-transfer research, metallurgy and ceramics, chemistry of high-temperature liquids, and radiation damage. The … more
Date: January 9, 1952
Creator: Briant, R. C.; Ellis, C. B. & Cottrell, William B.
Partner: UNT Libraries Government Documents Department
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Use of Steam-Electric Power Plants to Provide Thermal Energy to Urban Areas

Description: This report presents the results of a study that argues the importance of providing thermal energy from steam-electric power plants to urban areas.
Date: January 1971
Creator: Miller, A. J.; Payne, H. R.; Lackey, M. E.; Samuels, G.; Heath, M. T.; Hagen, E. W. et al.
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 details ongoing research at the Oak Ridge National Laboratory as a part of the Aircraft Nuclear Propulsion Project. Topics discussed include reactor theory and design, [part two is not included], materials research, and appendixes with information on analytical chemical studies.
Date: October 23, 1952
Creator: Briant, R. C.; Buck, J. H.; Miller, A. J. & Cottrell, William B.
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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Statistical Evaluation of Methods for the Analysis of Dibasic Aluminum Nitrate (DIBAN)

Description: The indicated methods for determining the following constituents of Diban, which is an aqueous solution of dibasic aluminum nitrate, Al(OH)2NO3, were evaluated statistically: 1aluminum by gravimetric, volumetric, and spectrophotometric procedures, 2. basicity (hydroxyl value) by formation of an aluminum complex and titration of the free acid with standard alkali solution, 3. total nitrogen by the Kjeldahl method, 4. ammonia by the Kjeldahl method, and 5. nitrates by means of a cation-exchange r… more
Date: September 16, 1955
Creator: Surak, J. G.; Thomason, P. F. & Haaen, H. P.
Partner: UNT Libraries Government Documents Department
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The Effects of Reactor Irradiation of Thorium-Uranium Alloy Fuel Plates

Description: Several plates of 98.7% Th - 1.2% U 235 (clad in aluminum) were irradiated in the MTR for an integrated flux of 2.6 x 10 21 neutrons/cm2. Although these samples represent an early development in bonding of aluminum to thorium and there are better methods at present, the bond proved to be quite strong and both clad and core were dimensionally stable under irradiation. The production of uranium 233 was as much as theory would indicate and the total amount of fissionable material material after ir… more
Date: September 7, 1955
Creator: Carrell, R. M.
Partner: UNT Libraries Government Documents Department
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ORNL Metal Recovery Plant Processing Clementine Reactor Fuel Elements: Terminal Report

Description: This report presents data obtained from processing 33 Clementine Reactor fuel elements in the ORNL Metal Recovery Plant to recover approximately 15 kg of plutonium and 0.16 g of americium.
Date: September 7, 1955
Creator: Matherne, J. L.; Brooksbank, R. K.; Campbell, D. O.; Chandler, J. M.; Rylton, C. D.; Leuse, R. E. et al.
Partner: UNT Libraries Government Documents Department
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Solid State Division Semiannual Progress Report for Period Ending August 31, 1955

Description: LITR Fluoride-Fuel Loop. — The inconel loop was dismantled for removal of the samples and for recovery of the uranium by using the remote cutting tools installed in a half cell of the Solid State Building. Disassembly proceeded without incident. An electric-arc cutting technique was developed for removal of the stainless steel enclosure around the pump bowl. Fission power and maximum flux were determined by irradiating a simulated loop, by heat-balance calculations, by radiochemical analyses fo… more
Date: November 16, 1955
Creator: Billington, D. S. & Crawford, J. H., Jr.
Partner: UNT Libraries Government Documents Department
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Determination of Corrosion Products and Additives in Homogeneous Reactor Fuel III. Polarographic Determination of Iron(III)

Description: An ion-exchange -- polarographic method was developed for the determination of iron(III) in Homogeneous Reactor Fuels. Copper, which interferes, is removed from the fuel by plating it onto a cadmium coil. Iron is oxidized to iron(III) by potassium permanganate, and the iron(III) is separated from interfering metal ions by ion exchange on a Dowex 1 resin column that is in the sulfate form. The iron(III) in the effluent is determined polarographically in 0.5 M sodium citrate solution as supportin… more
Date: October 24, 1955
Creator: Horton, A. D.; Thomason, P. F. & Raaen, H. P.
Partner: UNT Libraries Government Documents Department
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