The X-Ray Spectra of Polonium Atomic Number 84 (open access)

The X-Ray Spectra of Polonium Atomic Number 84

From abstract: "Two samples, each containing an estimated 10 curies (2 mg) of polonium-210, were purified by vacuum distillation and evaporated onto oblique sections of X-ray targets made of copper. Four lines of the K series and ten lines of the L series of the X-ray spectrum of polonium were recorded with a one-meter transmission crystal spectrograph and a 25-centimeter Bragg spectrograph, respectively. Measured wavelengths agree approximately with values predicted by extrapolation of Moseley's law and with those claimed by Hulubei. Decay of polonium-210 (half life = 138 days) and growth of lead-206 (stable) were observed over a period of 180 days."
Date: April 15, 1952
Creator: Peed, W. F.; Burkhart, L. E.; Staniforth, R. A. & Fauble, L. G.
System: The UNT Digital Library
Continuous Solvent Recovery Process Using Pulse Contacting Column (open access)

Continuous Solvent Recovery Process Using Pulse Contacting Column

From abstract: "This report presents the progress in the laboratory development of a continuous solvent recovery process for the tributyl phosphate-diluent mixture used in the Purex Process. Investigations were made with 1/2" diameter pulse columns, using a nine foot sodium carbonate contacting column and a four foot water wash column."
Date: April 1, 1952
Creator: Ellison, C. V. & Land, J. F.
System: The UNT Digital Library
Summary of Operating Experience with Decelerating Ion Receivers (open access)

Summary of Operating Experience with Decelerating Ion Receivers

From abstract: "The following report presents a summary of operating experience with decelerating receivers for ion beam reception. Sample calculations for design of such a receiver for the isotopes of lithium are presented. Estimates of maximum production and requirements to attain such production are given. The maximum ion beam envisioned is 17 amperes obtained from extrapolation of experimental results."
Date: April 1, 1952
Creator: Wilkinson, P. E. & Keim, C. P.
System: The UNT Digital Library
Recovery of Nitrogen Oxides and Rare Gas Fission Products From the Nitric Acid Dissolution of Irradiated Uranium (open access)

Recovery of Nitrogen Oxides and Rare Gas Fission Products From the Nitric Acid Dissolution of Irradiated Uranium

From abstract: "Data obtained in laboratory studies of the 'fumelses dissolving' of irradiated uranium are presented. Procedures for handling dissolver off-gases are proposed."
Date: April 30, 1952
Creator: Gresky, A. T.; Snyder, M. D.; Blair, J. A.; Lovelace, R. C.; Corbin, L. T. & Tyson, W. R.
System: The UNT Digital Library
Metallurgy Division Quarterly Progress Report: Period Ending October 31, 1951 (open access)

Metallurgy Division Quarterly Progress Report: Period Ending October 31, 1951

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.
System: The UNT Digital Library
Production of Fuel Assemblies for the Materials Testing Reactor Mock-Up Critical Experiments (open access)

Production of Fuel Assemblies for the Materials Testing Reactor Mock-Up Critical Experiments

Technical report outlining the fabrication of twenty-five fuel assemblies and three shim-safety rod fuel sections for use in the Materials Resting Reactor Mock-Up Critical Experiments. Results show that two of the assemblies exceeded tolerance in a few of the key dimensions, but were considered acceptable and as a consequence, production was carried out with no rejects. [From Abstract]
Date: April 9, 1951
Creator: Smith, C. D.; Drosten, F. W. & Kerze, F., Jr.
System: The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: November 15, 1951 (open access)

Homogeneous Reactor Project Quarterly Progress Report: November 15, 1951

From summary: "Construction of the HRE facility was essentially complete on November 15, 1951 except for minor revisions and final testing. A program of engineering and nuclear tests of the system hasbeen drawn up, and the tests will be started early in the next quarter. The only major HRE items for which design is not complete are the samplers for the fuel, [gas], and reflector systems. These will be completed in time to be installed before critical experiments begin; meanwhile, temporary sampling devices have been installed for use during the testing program."
Date: April 1, 1952
Creator: Swartout, J. A.; Secoy, C. H.; Welton, T. A.; Winters, C. E. & Thompson, W. E.
System: The UNT Digital Library
Fabrication Development of UO2-Stainless Steel Composite Fuel Plates for core B of the Enrico Fermi Fast Breeder Reactor (open access)

Fabrication Development of UO2-Stainless Steel Composite Fuel Plates for core B of the Enrico Fermi Fast Breeder Reactor

Experimental work concerned with the development of an inexpensive composite fuel plate with a high burnup potential for application in a 500°C sodium environment as Core B of the Enrico Fermi Fast Breeder Reactor.
Date: April 18, 1961
Creator: Cherubini, J. H.; Beaver, R. J. & Leitten, C. F., Jr.
System: The UNT Digital Library
Polfit II, an IBM 7090 Program for Polynomial Least Squares Fitting (open access)

Polfit II, an IBM 7090 Program for Polynomial Least Squares Fitting

Program written to perform polynomial least squares fits on the the IBM 7090 computer.
Date: April 24, 1961
Creator: Lietzke, M. P.
System: The UNT Digital Library
Maritime Reactor Project Annual Progress Report: for Period Ending November 30, 1962 (open access)

Maritime Reactor Project Annual Progress Report: for Period Ending November 30, 1962

Report documenting research and developments made by the Maritime Reactor Program of the Oak Ridge National Laboratory.
Date: April 4, 1963
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: November 1959-January 1960 (open access)

Homogeneous Reactor Project Quarterly Progress Report: November 1959-January 1960

From Summary: "The major objective of the run was the investigation of fuel stability. The reactor operated for long periods at the design power of 5 Mw with none of the usual indications of instability while the system pressure was kept at 1250 psig. Run 21 ended on January 22, so that the reason for an abrupt change in the mixing rate of fuel between the core and blanket could be investigated and a reactor steam-system valve could be repaired."
Date: April 29, 1960
Creator: Briggs, R. B.
System: The UNT Digital Library
Mathematics Panel: Annual Progress Report for Period Ending December 31, 1960 (open access)

Mathematics Panel: Annual Progress Report for Period Ending December 31, 1960

Programming research in the construction of a translator to Oracle language from ALGOL.
Date: April 6, 1961
Creator: unknown
System: The UNT Digital Library
The Decomposition of Diphosphopyridinenucleotide (DPN) and Adenosinetriphosphate (ATP) by Ultraviolet Light (open access)

The Decomposition of Diphosphopyridinenucleotide (DPN) and Adenosinetriphosphate (ATP) by Ultraviolet Light

Resolution of the products of the reactions of DPN and ATP with ultraviolet light by techniques of partition paper chromatography is reported in this paper.
Date: April 28, 1949
Creator: Carter, C. E.
System: The UNT Digital Library
Nuclear Superheat Project Fabrication, Irradiation and Evaluation of Superheat Fuel Element SH-1 and SH-2 (open access)

Nuclear Superheat Project Fabrication, Irradiation and Evaluation of Superheat Fuel Element SH-1 and SH-2

The fabrication, irradiation and evaluation of the first two superheat fuel assemblies is described in detail. Experimental data indicate that, in general, the nuclear superheat fuel elements have performed satisfactorily under the testing conditions used. Certain problem areas which will influence future fuel element designs have been defined.
Date: April 7, 1960
Creator: Lees, E. A.; Boyle, R. F. & Spalaris, C. N.
System: The UNT Digital Library
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Sixth Quarterly Report, January-March 1963 (open access)

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Sixth Quarterly Report, January-March 1963

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: April 1963
Creator: Leitz, F. J.
System: The UNT Digital Library
Fuel Cycle Program Progress Report: Eleventh Quarter, January-March 1963 (open access)

Fuel Cycle Program Progress Report: Eleventh Quarter, January-March 1963

Quarterly progress report discussing activities related to the Vallecitos Boiling Water Reactor (VBWR) and related facilities.
Date: April 5, 1963
Creator: Howard, C. L.
System: The UNT Digital Library
Spectra of Gamma Rays Produced by the INteraction of ~160-MeV Protons with Be, C, O, Al, Co, and Bi (open access)

Spectra of Gamma Rays Produced by the INteraction of ~160-MeV Protons with Be, C, O, Al, Co, and Bi

Report concerning the production of gamma ray spectra of gamma rays by the interaction of ~160-MeV protons with beryllium, carbon, oxygen, Aluminum, carbon monoxide, and bismuth. This also includes descriptions of the apparatus used and a discussion of the results.
Date: April 1965
Creator: Zobel, W.; Maienschein, F. C. & Scroggs, R. J.
System: The UNT Digital Library
Thorium-Uranium-233 Oxide (Kilorod) Facility : Rod Fabrication Process and Equipment (open access)

Thorium-Uranium-233 Oxide (Kilorod) Facility : Rod Fabrication Process and Equipment

Report documenting "the design, construction, and operation of the Kilorod Facility and its fabrication equipment" (p. 42) as well as its economic viability.
Date: April 1964
Creator: Sease, J. D.; Lotts, A. L. & Davis, F. C.
System: The UNT Digital Library
Some Major Fuel-Irradiation Test Facilities of the Oak Ridge National Laboratory (open access)

Some Major Fuel-Irradiation Test Facilities of the Oak Ridge National Laboratory

Report describing various reactors, six thermal conduction capsules, three loop facilities, miscellaneous equipment, and shop facilities maintained by the Oak Ridge National Laboratory.
Date: April 1964
Creator: Trauger, Donald B.
System: The UNT Digital Library
An Elliptic Integral Computer Package for Magnetic Fields, Forces, and Mutual Inductances of Axisymmetric Systems, and a Versatile Line-Tracing Routine (open access)

An Elliptic Integral Computer Package for Magnetic Fields, Forces, and Mutual Inductances of Axisymmetric Systems, and a Versatile Line-Tracing Routine

Report describing a set of high-precision routines for the IBM 7090 that perform efficiently the calculations most often required on axially symmetric magnetic systems. The routines compute the vector potential, field components, and the mixed gradient for current systems and for certain idealized distributions of magnetized matter. The programs for the current systems were developed from a set of six equations in elliptic integrals, which suffice when correlations are fully exploited for all the relevant properties of loops and solenoids.
Date: April 1965
Creator: Garrett, M. W.
System: The UNT Digital Library
Army Reactors Program Annual Progress Report: 1962 (open access)

Army Reactors Program Annual Progress Report: 1962

Report summarizing ongoing nuclear work performed by the ORNL for the United States Army.
Date: April 10, 1963
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Gas-Cooled Reactor Project Quarterly Progress Report: December 1961 (open access)

Gas-Cooled Reactor Project Quarterly Progress Report: December 1961

Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project.
Date: April 6, 1962
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Measurement of α, the Ratio of the Neutron Capture Cross Section to the Fission Cross Section, for ²³⁵U in the Energy Region from 3.25 eV to 1.8 keV (open access)

Measurement of α, the Ratio of the Neutron Capture Cross Section to the Fission Cross Section, for ²³⁵U in the Energy Region from 3.25 eV to 1.8 keV

Report issued by the Oak Ridge National Laboratory discussing techniques to obtain measurements of alpha for enriched uranium. Descriptions of equipment and experiments used to obtain alpha are presented. This report includes tables, and illustrations.
Date: April 1965
Creator: deSaussure, G.; Weston, L. W.; Gwin, R.; Russell, J. E. & Hockenbury, R. W.
System: The UNT Digital Library
Optical Mapping of Oak Ridge Research Reactor Experiment Tubes (open access)

Optical Mapping of Oak Ridge Research Reactor Experiment Tubes

Report issued by the Oak Ridge National Laboratory discussing optical mapping of experiment tubes. Descriptions of experiment equipment, and designs of the tubes are presented. This report includes tables, illustrations, and photographs.
Date: April 1965
Creator: Abbatiello, A. A.
System: The UNT Digital Library