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Best Match Title Creator Date Created (Newest) Date Created (Oldest) Date Added (Newest) Date Added (Oldest)
INDUSTRIAL CRITICALITY MEASUREMENTS ON ENRICHED URANIUM AND PLUTONIUM. PART II (open access)

INDUSTRIAL CRITICALITY MEASUREMENTS ON ENRICHED URANIUM AND PLUTONIUM. PART II

ABS>A series of neutron multiplication measurements made on sub-critical systems containing enriched uranium and plutonium is presented. These measurements involve both aqueous and metal systems. (auth)
Date: January 10, 1962
Creator: Schuske, C.L.; Bell, C.L.; Bidinger, G.H. & Smith, D.F.
Object Type: Report
System: The UNT Digital Library
A Method of Determining the Intermediate Energy Neutron Dose (open access)

A Method of Determining the Intermediate Energy Neutron Dose

The intermediate energy neutron flux existing outside the biological shielding of reactors has not been studied to any great extent previous to this time, because of the lack of an instrument capable of detecting neutrons in the intermediate energy range. The instrument used at the MTR utilizes polyethylene spheres of various sizes to give different amounts of moderation and absorption to the impinging neutrons. A procedure for the approximate determination of the relative number of intermediate energy and fast neutrons is given. By graphical methods the following information is obtained: (1) fraction of intermediate neutrons, (2) fraction of fast neutrons, and (3) the approximate average energy of the fast neutrons. Since the instrument described can be used to determine the thermal neutron flux independent of intermediate and fast fluxes, only one instrument is required to determine the neutron flux in all three energy ranges. Dose calculations indicate the intermediate range neutrons give a dose greater than the dose delivered by fast neutrons around the MTR-ETR reactors under normal operating conditions. (auth)
Date: March 10, 1961
Creator: Hankins, D. E.
Object Type: Report
System: The UNT Digital Library
Experimental observations and model calculations of impurity radiation in a plasma gun compact torus experiment (open access)

Experimental observations and model calculations of impurity radiation in a plasma gun compact torus experiment

Several types of radiation measurements were performed on the Beta II compact forms experiment. Among these are time integrated spectra ranging in wavelength from the vuv to the uv, time resolved bolometer measurements of radiation from the x-ray to the infrared, and time and wavelength resolved measurements of certain spectral lines. It is difficult to relate any one of these measurements to plasma parameters of interest such as temperature, density, or impurity content. In this report we compare the results of these, and other measurements with two simple models of the power balance in the plasma in order to estimate the effect of carbon and oxygen impurities on plasma lifetime.
Date: August 10, 1982
Creator: Goldenbaum, G. C.; Granneman, E. H. A.; Hartman, C. W.; Prono, D. S.; Taska, J. & Turner, W. C.
Object Type: Report
System: The UNT Digital Library
The Ornl Analytical Chemistry Division's 150-Kv Cockcroft-Walton Generator (open access)

The Ornl Analytical Chemistry Division's 150-Kv Cockcroft-Walton Generator

A general description of the facilities used to house a small Cockcroft- Walton generator is presented. Preliminary irformation and data are given as to the operational performance of the generator, the radiation safety controls involved, and the expected use of the device, In addition, an automatic-manual device for control of tritium target usage is described. (auth)
Date: September 10, 1962
Creator: Strain, J. E.; Hampton, W. J. & Leddicotte, G. W.
Object Type: Report
System: The UNT Digital Library
Time series analysis of reactor thermocouple data. [LMFBR] (open access)

Time series analysis of reactor thermocouple data. [LMFBR]

Time-series analysis techniques are applied to nuclear reactor thermocouple data to investigate coolant temperatures measured within the fueled test assembly. The coolant temperature distribution within a fuel assembly affects the length of time a fuel assembly may be operated in a power reactor and, therefore, is an important economic consideration in the design of reactor fuel systems. Frequency-domain signal conditioning techniques were used to reveal the smoothly varying thermocouple signals from the noisy digital data. Examination of the cross-correlation function for thermocouple pairs suggested an alternate surging and ebbing of coolant flow within certain zones of the fuel assembly. These zones corresponded to thermocouples which experienced higher or lower than predicted coolant temperatures. This time series analysis contributed greatly toward the understanding of fuel assembly thermal hydraulics.
Date: April 10, 1980
Creator: Devary, J.L.
Object Type: Article
System: The UNT Digital Library
CHARGING AND DISCHARGING OF DEMINERALIZER RESINS. CORE I, SEED 2. Test Results (T-612085). Section 1 (open access)

CHARGING AND DISCHARGING OF DEMINERALIZER RESINS. CORE I, SEED 2. Test Results (T-612085). Section 1

An investigation was conducted to flush the 1BD coolant purification system demineralizer of resin and to measurc the radiation level at pornts on the resin discharge line. It was found that the system demineralizer was satisfactorily flushed of resin. It was also found that the amount removed is measured by the amount required to recharge the demineralizer. (J.R.D.)
Date: January 10, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Pyrolysis of Wyoming subbituminous coal. [Pyrolysis at 500 and 625/sup 0/C; gas evolution and tar production may play significant roles in in-situ coal gascation; pyrolysis gas mainly CO/sub 2/, CO, H/sub 2/, and CH/sub 4/] (open access)

Pyrolysis of Wyoming subbituminous coal. [Pyrolysis at 500 and 625/sup 0/C; gas evolution and tar production may play significant roles in in-situ coal gascation; pyrolysis gas mainly CO/sub 2/, CO, H/sub 2/, and CH/sub 4/]

None
Date: March 10, 1975
Creator: Macknick, A.B.
Object Type: Report
System: The UNT Digital Library
Kilowatt Isotope Power System: component test procedure for the ground demonstration system jet condenser orifice performance. 77-KIPS-83 (open access)

Kilowatt Isotope Power System: component test procedure for the ground demonstration system jet condenser orifice performance. 77-KIPS-83

The verification methods which shall be used in the development program to be conducted on the Kilowatt Isotope Power System (KIPS) Jet Condenser to verify adequate orifice thermal performance are described. The purpose of the test procedure is to determine which orifice elements achieve satisfactory thermal performance to assure adequacy for Ground Demonstration System (GDS) Testing.
Date: August 10, 1977
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Superconductivity in solid solutions of transition metal carbides. [NbC-TaC] (open access)

Superconductivity in solid solutions of transition metal carbides. [NbC-TaC]

None
Date: June 10, 1964
Creator: Wells, M.
Object Type: Report
System: The UNT Digital Library
Numerical Analysis of Neutron Resonances (open access)

Numerical Analysis of Neutron Resonances

Neutron resonances are analyzed numerically by determining the resonant energies, the total widths, and the neutron widths of the resonances. It was assumed that the total cross section can be represented by the sum of single- level Breit-Wigner formulas, with interference between resonance and potential scattering but no interference between resonances; that the Doppler broadening is represented by a Gaussian function; and that the instrument resolution is represented by a Gaussian function. Gauss' method was used to reduce the nonlinear problem to one in which linear methods can be applied. Some unusual techniques were used for evaluating the integrals in the function for calculating the transmission. Two programs for analyzing transmission data to obtain the parameters of the resonances were written for the IBM 7090 computer. The first program is a shape analysis for determining the resonant energies, the total widths, and the neutron widths of the resonances. This program analyzes the transmission data for as many as six resonances at once. The second program is an area analysis for determining the neutron widths of the resonances for assumed total widths. This program analyzes transmission data containing as many as 20 resonances at once. (auth)
Date: January 10, 1962
Creator: Atta, S.E. & Harvey, J.A.
Object Type: Report
System: The UNT Digital Library
Measurements of pressure for the TiH/sub x//KClO/sub 4/ system (open access)

Measurements of pressure for the TiH/sub x//KClO/sub 4/ system

An investigation was conducted to measure the pressure obtained when the pyrotechnic mixture TiH/sub x//KClO/sub 4/ was ignited in a confined variable-volume system. It was possible to derive an expression of the form PV/sup ..gamma../ = k for the pressure-volume relationship obtained. This expression is a polytropic expansion of the ideal gas equation that best fits the data generated. For this particular work, values of ..gamma.. = 0.53 and k = 69.3 were obtained where P is in megapascals and V is in cubic centimeters. In addition, estimates of the reaction rates were calculated based on the times to achieve maximum pressure for a given volume system. An explicit expression relating rate to pressure was derived by a simplified least-squares fit of the data obtained.
Date: April 10, 1978
Creator: Chong, C. H. H. & Glaub, J. E.
Object Type: Report
System: The UNT Digital Library
IN-PILE GAS-COOLED FUEL ELEMENT TEST FACILITY (open access)

IN-PILE GAS-COOLED FUEL ELEMENT TEST FACILITY

Paper presented at American Nuclear Society Meeting, June I8-21, 1962, Boston, Mass. Design and operating problems of unclad and ceramic gas-cooled reactor fuels in high temperature circulating gas systems will be studied using a test facility now nearing completion at the Oak Ridge Research Reactor. A shielded air-tight cell houses a closed circuit gas system equipped for dealing with fission products circulating in the gas. Experiments can be conducted on fuel element performance and stability, fission product deposition, gas clean up, activity levels, component and system performance and shielding, and decontamination and maintenance of system hardware. (auth)
Date: July 10, 1962
Creator: Zasler, J.; Huntley, W. R.; Gnadt, P. A. & Kress, T. S.
Object Type: Report
System: The UNT Digital Library
OGRE-P2, a Monte Carlo Program for Computing Gamma-Ray Leakage From Laminated Slabs With a Distributed Source (open access)

OGRE-P2, a Monte Carlo Program for Computing Gamma-Ray Leakage From Laminated Slabs With a Distributed Source

A Monte Carlo program OGRE-P2 was written for the IBM-7090 to solve the problem of gamma radiation from a slab of laminated regions composed of various materials. The dose rate is calculated on one side of the slab. (J.R,D.)
Date: August 10, 1962
Creator: Trubey, D. K.; Penny, S. K. & Emmett, M. B.
Object Type: Report
System: The UNT Digital Library
THE FABRICATION AND IRRADIATION TESTING OF DISPERSION-TYPE BeO-UO$sub 2$ CERAMIC FUEL MATERIALS (open access)

THE FABRICATION AND IRRADIATION TESTING OF DISPERSION-TYPE BeO-UO$sub 2$ CERAMIC FUEL MATERIALS

Considerations affecting the design of dispersion-type ceramic fuel materials are discussed. The results of measurements made to study the effect of fuel loading on the properties of the fuel bodies and the results of irradiation tests of fuel pellets composed of 20 vol% UO/sub 2/ dispersed in BeO are presented. Experience in the fabrication of dispersion-type BeO --UO/sub 2/ ceramic fuel materials is described. From the results obtained, it is believed that BeO --UO/sub 2/ fuel materials of the type studied will exhibit satisfactory performance in the Experimental Beryllium Oxide Reactor. (auth)
Date: October 10, 1962
Creator: Johnson, D. E. & Lofftus, F. H.
Object Type: Report
System: The UNT Digital Library
Microearthquakes in geothermal prospecting (open access)

Microearthquakes in geothermal prospecting

None
Date: December 10, 1974
Creator: Lange, A.L.
Object Type: Article
System: The UNT Digital Library
Ocean Thermal Energy Conservation (OTEC) power system development (PDS) II. Preliminary design report (open access)

Ocean Thermal Energy Conservation (OTEC) power system development (PDS) II. Preliminary design report

This report documents the results and conclusions of the PDS II, Phase I, preliminary design of a 10 MWe OTEC power system, using enhanced plate type heat exchangers, and of representative 0.2 MWe test articles. It further provides the documentation (specifications, drawings, trade studies, etc.) resulting from the design activities. The data and discussions of the technical concepts are organized to respond to the PDS II, Phase II proposal evaluation criteria. This volume, which specifically addresses the three evaluation categories (heat exchangers, rotating machinery, and power system configuration and performance) is an integral part of the Phase II plans (proposal) which describe the technical approach to delivering test articles to OTEC-1. In addition, there is a section which addresses power system cost and net energy analysis and another which discusses the results of stainless steel feasibility studies. Supporting documentation is contained in two appendix volumes.
Date: August 10, 1979
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Pilot demonstration-enhanced oil recovery by micellar-polymer waterflooding Bell Creek Field. Monthly technical progress report, August 1977 (open access)

Pilot demonstration-enhanced oil recovery by micellar-polymer waterflooding Bell Creek Field. Monthly technical progress report, August 1977

This is the fourteenth Monthly Technical Progress Report submitted under ERDA Contract No. EY-77-C-02-4207, formerly Contract No. E(49-18)-2237. As such it continues the coverage of the activities undertaken by Gary Operating Company, as well as by the major subcontractors, Atlantic Richfield, Union Oil and Intercomp. The work described covers the tasks for: Micellar-Polymer Systems Selection and Evaluation, Site Development, Pilot Performance Predictions and Fluid Distribution Facilities. The major activity at this time is Phase II, Task 1, the Micellar-Polymer Systems Selection as between the two competing designs being developed by Atlantic Richfield and Union Oil. This activity came to closure with Decision Point 2 on August 24, 1977.
Date: September 10, 1977
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Benchmark field study of deep neutron penetration (open access)

Benchmark field study of deep neutron penetration

A unique benchmark neutron field has been established at the Lawrence Livermore National Laboratory (LLNL) to study deep penetration neutron transport. At LLNL, a tandem accelerator is used to generate a monoenergetic neutron source that permits investigation of deep neutron penetration under conditions that are virtually ideal to model, namely the transport of mono-energetic neutrons through a single material in a simple geometry. General features of the Lawrence Tandem (LATAN) benchmark field are described with emphasis on neutron source characteristics and room return background. The single material chosen for the first benchmark, LATAN-1, is a steel representative of Light Water Reactor (LWR) Pressure Vessels (PV). Also included is a brief description of the Little Boy replica, a critical reactor assembly designed to mimic the radiation doses from the atomic bomb dropped on Hiroshima, and its us in neutron spectrometry. 18 refs.
Date: June 10, 1991
Creator: Morgan, J. F.; Sale, K. (Lawrence Livermore National Lab., CA (USA) ); Gold, R.; Roberts, J. H. & Preston, C. C. (Metrology Control Corp., Richland, WA (USA) )
Object Type: Article
System: The UNT Digital Library
January 1978 monthly highlights for Office of Nuclear Regulatory Research Programs at Oak Ridge National Laboratory (open access)

January 1978 monthly highlights for Office of Nuclear Regulatory Research Programs at Oak Ridge National Laboratory

Highlights of technical progress during January 1978 are presented for sixteen separate program activities which comprise the ORNL research program for the Office of Nuclear Regulatory Research's Division of Reactor Safety Research.
Date: February 10, 1978
Creator: Mynatt, F.R. (comp.)
Object Type: Report
System: The UNT Digital Library
Americium purification by a combined anion exchange and bidentate organophosphorus solvent extraction process. [Patent application] (open access)

Americium purification by a combined anion exchange and bidentate organophosphorus solvent extraction process. [Patent application]

Americium is separated from mixtures containing plutonium, other actinides, and other non-lanthamide impurities, by a combined process of anion exchange resin sorption to remove plutonium, and a bidentate organophosphorus solvent extraction of americium of the anion exchange resin effluent. Dihexyl-N,N-diethylcarbamylmethylenephosphonate is a preferred solvent. The initial mixture may be subjected to a cation exchange operation to remove monovalent impurities. The process is especially effective when aluminum, zinc, lead, and copper are present in significant quantities in the original mixture.
Date: April 10, 1981
Creator: Navratil, J.D. & Martella, L.L.
Object Type: Patent
System: The UNT Digital Library
[News Clip: Coke contest] captions transcript

[News Clip: Coke contest]

Video footage from the WBAP-TV station in Fort Worth, Texas to accompany a story about Mrs. Lota Haverty, who is one of the second prize winners in the Coca-Cola company's sweepstakes contest, where she has the choice of one thousand dollars cash or an expense-paid visit to the New York World's Fair for herself and four friends.
Date: June 10, 1964
Creator: WBAP-TV (Television station : Fort Worth, Tex.)
Object Type: Video
System: The UNT Digital Library
Fundamental studies of catalytic processing of synthetic liquids (open access)

Fundamental studies of catalytic processing of synthetic liquids

This project revolves around understanding the fundamental processes involved in the catalytic removal of harmful oxygenated organics present in coal liquids. We will model the complex type of sulfided Mo catalyst proposed for these reactions with a simple single crystal surfaces that display a controlled range and number of reaction sites and can be extensively characterized by surface science techniques.
Date: April 10, 1990
Creator: Watson, P. R.
Object Type: Report
System: The UNT Digital Library
Super-Prompt-Critical Behavior of an Unmoderated Unreflected Uranium- Molybdenum Alloy Assembly (open access)

Super-Prompt-Critical Behavior of an Unmoderated Unreflected Uranium- Molybdenum Alloy Assembly

The time-dependent behavior was investigated of the neutron population in an unreflected unmoderated cylindrical assembly of 90 wt.% U (93.2 wt.% U/sup 235/), 10 wt.% Mo alloy following rapid establishment of a super-prompt critical c ondition with negligible initial neutron population. Reactivity increases up to 11 cents above prompt critical resulted in bursts yielding as many as 1.8 x 10/ sup 17/ fissions with reactor periods as short as 16 mu sec and temperature increases as large as 400 deg C. Pressure waves generated in a portion of the core held in position by an electromagnet for bursts greater than ~6 x 10/sup 16/ fissions initiated the removal of this section about 225 mu sec after the peak burst. (auth)
Date: May 10, 1962
Creator: Mihalczo, J.T.
Object Type: Report
System: The UNT Digital Library
Steady State Thermal Behavior of Hnpf Sodium Heat Transfer System (open access)

Steady State Thermal Behavior of Hnpf Sodium Heat Transfer System

The performance of the Hallam Nuclear Power Facility heat transfer components was investigated in order to determine the steady-state, part load characteristics under various operating conditions. The complete steady-state temperature distributions, variations of flow rates and heat transfer coefficients throughout the sodium heat transfer systems as functions of reactor load are shown in a series of graphs. (M.C.G.)
Date: August 10, 1959
Creator: Stell, A.T.
Object Type: Report
System: The UNT Digital Library