Preliminary Report on the Hydrolytic Behavior of Cerium (IV) (open access)

Preliminary Report on the Hydrolytic Behavior of Cerium (IV)

The following report analyzes the hydrolytic behavior of cerium and compares them with the actinides of uranium and plutonium.
Date: May 25, 1948
Creator: Kraus, K. A.; Holmberg, R. W. & Nelson, F.
System: The UNT Digital Library
Studies of Porphyrin Metabolism, 3. The Relation of Erythropoiesis to the Excretion of Coproporphyrin by Dogs and Rabbits, and to the Concentration of Coproporphyrin and Protoporphyrin in Rabbit Erythrocytes (open access)

Studies of Porphyrin Metabolism, 3. The Relation of Erythropoiesis to the Excretion of Coproporphyrin by Dogs and Rabbits, and to the Concentration of Coproporphyrin and Protoporphyrin in Rabbit Erythrocytes

Report discussing studies regarding porphyrin excretion and hemoglobin metabolism in animals with phenylhydrazine anemia, and studies regarding the coproporphyrin and protoporphyrin in the red blood cells of rabbits.
Date: November 25, 1945
Creator: Schwartz, Samuel; Glickman, Marcia; Hunter, Rosie & Wallace, Jean
System: The UNT Digital Library
The Ratio of Amino Acid Nitrogen to Creatinine in the Urine as a Sensitive Test for Uranium Poisoning (open access)

The Ratio of Amino Acid Nitrogen to Creatinine in the Urine as a Sensitive Test for Uranium Poisoning

Report discussing experiments that were performed to determine whether amino acids in urine could be used as a test of subtle uranium poisoning.
Date: May 25, 1948
Creator: Berke, Harry & Rothstein, A.
System: The UNT Digital Library
Iodine Exchange Reaction (open access)

Iodine Exchange Reaction

This report discusses an analysis on the exchange reaction between iodine and unipositive iodine with pyridine.
Date: August 25, 1948
Creator: Kleinberg, Jacob & Sattizahn, James
System: The UNT Digital Library
Direct Current Electromagnetic Pumps (open access)

Direct Current Electromagnetic Pumps

Abstract: "A number of direct current conduction type electromagnetic pumps for liquid metals were constructed. Pumping capacities of over 400 gpm and efficiencies of over 50 percent were obtained. NaK alloy at temperatures up to 400 C was used in the test. The large currents required were obtained from rectifiers or from a homopolar generator constructed for the purpose."
Date: October 25, 1949
Creator: Barnes, A. H.; Smith, F. A. & Whitham, G. K.
System: The UNT Digital Library
Neutron Streaming in Steel: The Dependence of the Streaming on the Nickel Content of the Steel (open access)

Neutron Streaming in Steel: The Dependence of the Streaming on the Nickel Content of the Steel

The following report analyzes whether there is a difference between the neutron streaming in the "armor plate" and 347 stainless steel.
Date: May 25, 1953
Creator: Schamberger, Robert D. & Shore, Ferdinand J.
System: The UNT Digital Library
Flux Distributions and Critical k [infinity] Values for Cylindrical Reactors Simulation the MTR (open access)

Flux Distributions and Critical k [infinity] Values for Cylindrical Reactors Simulation the MTR

From summary: "In order to estimate the effect of placing bismuth and thorium layers near the MTR core, radial flux distributions and k[infinity] values were calculated for cylindrical reactors having cylindrical layers of these materials of the same height as the core and beryllium reflector and placed either next to the core or embedded in the beryllium reflector."
Date: June 25, 1952
Creator: Bray, D. T. & McMurry, Henry Lewis, {}
System: The UNT Digital Library
Factors Affecting the Penta-Ether Extraction Uranium (open access)

Factors Affecting the Penta-Ether Extraction Uranium

This report discusses the contributions of the workers at Tennessee Eastman Corporation in the investigation of limiting conditions in the application of penta-ether (aka. dibutoxytetraethylene).
Date: July 25, 1947
Creator: Musser, D. F.; Krause, D. P. & Smellie, Robert H.
System: The UNT Digital Library
Critical Dimensions of Untamped Conical Vessels (open access)

Critical Dimensions of Untamped Conical Vessels

Abstract: "The need often arises for determining the critical chemical concentration of uranium solution in the conical bottom of a plant reactor or storage vessel, or the dimension if the concentration is known. This report describes the mathematical analysis of Poisson's equation for a spherical sector, which approximates a right circular cone. The ratio of the critical dimension of an equivalent sphere to the height of the sector for various sector angles is derived from a comparison of first eigenvalues. No description of further relations between composition and dimensions is discussed in the report."
Date: August 25, 1947
Creator: Murray, Raymond
System: The UNT Digital Library
Materials Testing Reactor Project : Addendum to Reactor Building Wing Report, Design Report No. 27A (open access)

Materials Testing Reactor Project : Addendum to Reactor Building Wing Report, Design Report No. 27A

"Changes, corrections and additions to the original report are included in this addendum. These are brought about by further development of the design by Blaw-Knox, AHL and ORNL. The changes in the original wiritings are listed below in accordance with the main headings, pages and paragraphs to which they apply. Following this is a list of the contemplated personnel in the MTR program. This listing sets out the number of offices and the office furniture requirements. Also numbers for lockers, showers, toilets and rest rooms are set forth. Although the listing includes all major buildings planned for the site, it is included here since the reactor building wing is more markedly influenced by office requirements."
Date: November 25, 1949
Creator: Link, L. E. & Guzik, R. F.
System: The UNT Digital Library
Temperature Rise in a Heat Producing Cylinder Under a Coating Defect (open access)

Temperature Rise in a Heat Producing Cylinder Under a Coating Defect

Abstract: "For defects between interior and coating, or between successive layers of coating, a simple, fairly accurate formula is established. The temperature rise at the edge of the defect is briefly discussed."
Date: January 25, 1944
Creator: Ginsburg, M.; Karush, W. & Young, G.
System: The UNT Digital Library
Development of the Higgins Continuous Ion Exchange Contactor for the Recovery of Uranium from Leached Ore Pulps (open access)

Development of the Higgins Continuous Ion Exchange Contactor for the Recovery of Uranium from Leached Ore Pulps

From introduction: "The objective of this report is to present the results and describe the tests of both the 2-in. D and 6-in. D contractors using mill pulp feeds. Work on determining resign attrition is also reported. ORNL-CF-52-12-101 described the results of preliminary tests using synthetic ore pulps."
Date: March 25, 1955
Creator: Higgins, I. R.; Hancher, C. W. & Arehart, T. A.
System: The UNT Digital Library
Direct Conversion of the TF₆ to TCl₄ (open access)

Direct Conversion of the TF₆ to TCl₄

The following report provides a general summary of some methods that could be used to convert hexafluoride into tetrafluoride, but is mainly devoted to the work done on the conversion of tetrafluoride to tetrachloride.
Date: September 25, 1945
Creator: Calkins, Vincent P.
System: The UNT Digital Library
A Precise Potentiometric Titration Method for the Determination of Uranium (open access)

A Precise Potentiometric Titration Method for the Determination of Uranium

Abstract: "A precise potentiometric method for the determination of uranium in essentially pure uranium oxides is described. Ten gram samples of oxides are reduced in a Jones reductor and titrated potentiometrically to U+4, using platinum and tungsten electrodes. A weighed amount of solid Bureau of Standards potassium dichromate is then used to oxidize at least 99 percent of the uranous ion, and the oxidation is completed by titration with 0.01 N potassium dichromate using calomel and platinum electrodes. This method, which is based on a primary chemical standard, has a precision of +/- 0.015% on a single determination at the 95 percent confidence interval."
Date: August 25, 1953
Creator: Voss, F. S. & Greene, R. E.
System: The UNT Digital Library
The Preparation and Physical Properties of Uranium Binary Alloys Containing Aluminum and Columbium (open access)

The Preparation and Physical Properties of Uranium Binary Alloys Containing Aluminum and Columbium

This report follows experiments conducted to determine an alloy addition agent for uranium which would subsequently increase the yield strength and creep resistance of uranium.
Date: September 25, 1950
Creator: Grobecker, D. W.; Arnold, W. F.; Taub, J. M. & Doll, D. T.
System: The UNT Digital Library
Spectrophotometric Determination of Silicon in Zirconium (open access)

Spectrophotometric Determination of Silicon in Zirconium

Report presenting background and instructions on completing spectrophotometric determination of silicon in zirconium, which relies on the solubility of silicon tetrachloride in a small amount of nitric acid solution and the complexing of fluorides with boric acid.
Date: February 25, 1951
Creator: Read, E. B. & Martin, J. P.
System: The UNT Digital Library
The Magnitude of the [gamma] Effect (open access)

The Magnitude of the [gamma] Effect

The following report follows a correction on a previous report (CP-1381) on the value of the magnitude of the gamma effect.
Date: April 25, 1951
Creator: Wigner, E. P.
System: The UNT Digital Library
Processing Leach Solutions From Pyrosulfate Fusions of Salvage Residues for the Recovery of Tuballoy (open access)

Processing Leach Solutions From Pyrosulfate Fusions of Salvage Residues for the Recovery of Tuballoy

Report discussing two methods for "the elimination of sulfate and second group interferences in the extraction of tuballoy from residues which have been processed by the pyrosulfate fusion method." Advantages for one of the methods are mentioned.
Date: January 25, 1946
Creator: Ryon, A. D.; Aikin, L. M. & Susano, C. D.
System: The UNT Digital Library
A Needle in a Haystack (open access)

A Needle in a Haystack

Abstract: "Production of [rho]'s and [omega]'s in [pi]- + p and p + [letter p with a bar over it] interactions is discussed. The [rho] is presumably a J = 1-, 1 = 1 state and thus can decay into 2[pi]'s via a strong coupling. The [omega] is probably J = 1-, 1 = 0 which can also decay into 2[pi]'s via electromagnetic coupling. A theoretical description of this situation is presented in terms of coupled time-dependent Schroedinger equations which mix [rho] and [omega] states that are assumed to be isotopically pure at the time of production. The interference between the two resonances was found to have the effect of extending the 2[pi] spectrum toward the [omega] mass."
Date: May 25, 1962
Creator: Bernstein, J. & Feinberg, Gerald, 1933-1992
System: The UNT Digital Library
Uranium Chemistry of Raw Materials Section Progress Report for October 1, 1951 to December 31, 1951 (open access)

Uranium Chemistry of Raw Materials Section Progress Report for October 1, 1951 to December 31, 1951

This progress report discusses the work during the fourth quarter of 1951. During this quarter, "the uranium raw materials program at ORNL has been devoted to studies of uranium chemistry and to the development of processes for deriving uranium and byproducts from various types of ores" (From introduction).
Date: January 25, 1952
Creator: Brown, K. B.
System: The UNT Digital Library
Forced Convection Heat Transfer in Thermal Entrance Regions Part III. Heat Transfer to Liquid Metals (open access)

Forced Convection Heat Transfer in Thermal Entrance Regions Part III. Heat Transfer to Liquid Metals

Technical report covering the work done to explore heat transfer analytically and experimentally in liquid metals in turbulent flow within the thermal entrance region of circular tubes having uniform well temperature. Includes implications of this research. [From Summary]
Date: June 25, 1954
Creator: Harrison, William B.
System: The UNT Digital Library
Corrosion Data From the ORNL Purex Pilot Plant Acid Recovery Equipment (open access)

Corrosion Data From the ORNL Purex Pilot Plant Acid Recovery Equipment

From abstract: "This report summarizes the corrosion data obtained for nine construction materials located throughout the ORNL Purex Pilot Plant Acid Recovery Unit during seven hundred hours of operation."
Date: March 25, 1952
Creator: Landry, J. W. & Ullmann, J. W.
System: The UNT Digital Library
An Experimental Determination of Fission Product Heating After Shutdown of the Low Intensity Training Reactor (open access)

An Experimental Determination of Fission Product Heating After Shutdown of the Low Intensity Training Reactor

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.
System: The UNT Digital Library
Mathematics Panel Quarterly Progress Report for the Period Ending January 31, 1952 (open access)

Mathematics Panel Quarterly Progress Report for the Period Ending January 31, 1952

This progress report discusses new additions to the Mathematics Panel and discusses new and further work happening at Oak Ridge National Laboratory relating to the Mathematics Panel, of particular note is the Oak Ridge computer which is being fabricated at Argonne National Laboratory and the Technitrol Company.
Date: April 25, 1952
Creator: Householder, Alston S., (Alston Scott), 1904-1993 & Perry, C. L.
System: The UNT Digital Library