Single particle behavior in plasmas (open access)

Single particle behavior in plasmas

The paper follows the history of a neutral atom or molecule into a plasma--ionization, dissociation, radiation,--until it becomes a set of charged particles moving in the electromagnetic fields of the plasma system. The various useful forms of the method of averaging are displayed and applied to calculation of constants of motion. The breakdown of these constants is discussed along with some of the implications for fusion systems.
Date: March 10, 1977
Creator: McNamara, B.
Object Type: Report
System: The UNT Digital Library
Analysis of Paraho oil shale products and effluents: an example of the multi-technique approach (open access)

Analysis of Paraho oil shale products and effluents: an example of the multi-technique approach

Inorganic analysis of solid, liquid and gaseous samples from the Paraho Semiworks Retort was completed using a multitechnique approach. The data were statistically analyzed to determine both the precision of each method and to see how closely the various techniques compared. The data were also used to determine the redistribution of 31 trace and major elements in the various effluents, including the offgas for the Paraho Retort operating in the direct mode. The computed mass balances show that approximately 1% or greater fractions of the As, Co, Hg, N, Ni, S and Se are released during retorting and redistributed to the product shale oil, retort water or product offgas. The fraction for these seven elements ranged from almost 1% for Co and Ni to 50 to 60% for Hg and N. Approximately 20% of the S and 5% of the As and Se are released. The mass balance redistribution during retorting for Al, Fe, Mg, V and Zn was observed to be no greater than .05%. These redistribution figures are generally in agreement with previous mass balance studies made for a limited number of elements on laboratory or smaller scale pilot retorts. 7 tables.
Date: June 10, 1979
Creator: Fruchter, J. S.; Wilkerson, C. L.; Evans, J. C. & Sanders, R. W.
Object Type: Article
System: The UNT Digital Library
Supporting Analysis for Thermal Suitability of Fuel Elements for SM-1A Core I Loading (open access)

Supporting Analysis for Thermal Suitability of Fuel Elements for SM-1A Core I Loading

A recommended SM-1A Core I loading chart was derived from available, metallurgically acceptable elements at the SM-1A and SM-1 sites. The derivation was based on local thermal and hydraulic considerations of minimum elementto- element coolant channel clearances. These clearances were determined from field inspection measurements of outer fuel plate spacing, as modified by analytical calculations of plate ripple growth during exposure to reactor operating thermal stresses. (auth)
Date: January 10, 1962
Creator: Brondel, J. O.
Object Type: Report
System: The UNT Digital Library
Extracted current densities from surface conversion sources of negative ions (open access)

Extracted current densities from surface conversion sources of negative ions

The condition for extracting a maximum negative ion current density is found when the product of the radius of the negative ion conversion electrode, the cross-section for negative and positive ion recombination, and the density of positive ions in the ion source equals one. The optimum output is obtained at the highest positive ion density and the smallest electrode radius.
Date: February 10, 1982
Creator: Fink, J.H.
Object Type: Report
System: The UNT Digital Library
Proceedings of the symposium on experiments using enriched antiproton, polarized proton, and polarized antiproton beams at Fermilab energies (open access)

Proceedings of the symposium on experiments using enriched antiproton, polarized proton, and polarized antiproton beams at Fermilab energies

The conference included 10 papers, one of which appeared previously under conference number Conf: 770675-1. Separate abstracts were prepared for the remaining nine papers. (JFP)
Date: June 10, 1977
Creator: Yokosawa, A. (ed.)
Object Type: Article
System: The UNT Digital Library
SOME EXPERIENCES IN THE WELD FABRICATION OF REFRACTORY METALS (open access)

SOME EXPERIENCES IN THE WELD FABRICATION OF REFRACTORY METALS

Discussion is given on the welding fabrication of tungsten, molybdenum, niobium, and tantalum. Properties which make the four refractory metals important are tabulatcd along with titanium which is given for comparison. Extensive evaluation was conducted using the gas, tungsten arc welding process employing both manual and machine welding. Design data were obtained exclusively from machine welded sheet materials. Flash welding, resistance spot welding and brazing, electron beam welding, and high frequency resistance welding processes were also applied to molybdenum alloys. The oxidation of molybdenum, tantalum, and niobium in flowing air at 2000 deg F is also given. (P.C.H.)
Date: February 10, 1961
Creator: Thompson, E.G.
Object Type: Report
System: The UNT Digital Library
Phase I of the Near-Term Hybrid Vehicle Program. Final report (open access)

Phase I of the Near-Term Hybrid Vehicle Program. Final report

Heat engine/electric hybrid vehicles offer the potential of greatly reduced petroleum consumption, compared to conventional vehicles, without the disadvantages of limited performance and operating range associated with pure electric vehicles. This report documents a hybrid vehicle design approach which is aimed at the development of the technology required to achieve this potential, in such a way that it is transferable to the auto industry in the near term. The development of this design approach constituted Phase I of the Near-Term Hybrid Vehicle Program. The major tasks in this program were: mission analysis and performance specification studies; design tradeoff studies; and preliminary design. Detailed reports covering each of these tasks are included as appendices to this report. A fourth task, sensitivity studies, is also included in the report on the design tradeoff studies. Because of the detail with which these appendices cover methodology and results, the body of this report has been prepared as a brief executive summary of the program activities and results, with appropriate references to the detailed material in the appendices.
Date: September 10, 1979
Creator: unknown
Object Type: Report
System: The UNT Digital Library
HANFORD STUDIES FOR EGCR COMBUSTION CHARACTERISTICS. Summary Report (open access)

HANFORD STUDIES FOR EGCR COMBUSTION CHARACTERISTICS. Summary Report

The temperature, geometry, and flow conditions which exist in the EGCR were duplicated in a mock-up designated as the EGCR Burning Rig to establish the combustion conditions in the reactor. The conditions under which the EGCR Burning Rig will ignite were established and an analytical model was developed which predicts these conditions. Because the Burning Rig cannot exactly dupIicate the reactor situation the final prediction of the safety of the EGCR must rest on computer calculations employing the above analytical model. No advantage in retarding combustion was found in using silicon carbide coated fuel sleeves. The negative results of these tests are due both to the particular geometry of the EGCR moderator and sleeves as well as to the fact that all sleeves tested contained imperfections in the coatings. Chlorine was demonstrated to be an effective agent for extinguishing graphite fires. Concentrations in air of about 1% were observed to extinguish graphite fires at temperatures as high as 1000 deg C. (auth)
Date: October 10, 1961
Creator: de Halas, D.R.; Dahl, R.E. & Jackson, J.L.
Object Type: Report
System: The UNT Digital Library
Tar sand extraction by steam stimulation and steam drive: measurement of physical properties (open access)

Tar sand extraction by steam stimulation and steam drive: measurement of physical properties

The measurement of the following thermophysical properties of Utah tar sands is in progress: thermal conductivity, specific heat relative permeability, and viscosity (of the recovered bitumen). During the report period (October 1, 1978 to November 1, 1979), experimental procedures have been developed and a basic data set has been measured. Additionally, standard core analysis has been performed for four drill sites in the Asphalt Ridge, Utah area.
Date: September 10, 1980
Creator: Linberg, W.R.
Object Type: Report
System: The UNT Digital Library
Delayed Failure Hydrogen Embrittlement of Zirconium. Summary Report, September 15, 1961 to September 14, 1962 (open access)

Delayed Failure Hydrogen Embrittlement of Zirconium. Summary Report, September 15, 1961 to September 14, 1962

The extent to which zirconium and zirconium alloys exhibit delayed failure (static fatigue) as caused by a combination of absorbed hydrogen and applied stress was investigated. Susceptibility to time-dependent fracture was evaluated for unalloyed zirconium and Zircaloy-2 with 200 and 500 ppm hydrogen as well as for an experimental Zr Al-Sn-Mo alloy and the Canadian Zr-2.5Nb cladding material. For unalloyed zirconium and Zircaloy-2 containing up to 500 ppm hydrogen, no room-temperature, timedependent fracture occurred which could be definitely attributed to the delayed failure phenomenon; an increased grain size, 20% cold deformation by rolling, or corrosion in 750 deg F steam did not significantly affect this behavior. The curve of applied stress versus time to failure at room temperature for the high-strength Zr-Al-Sn--Mo alloy containing 500 ppm hydrcgen established a strong susceptibility to delayed failure due to hydrogen absorption; studies on vacuum-annealed material showed no failures. Further, reduced temperature indicated that the occurrence of static fatigue is temperature dependent. Data for heattreated Zr 2.5Nb containing 500 ppm hydrogen indicated that this material is moderately sensitive to delayed failure at room temperature; higher hydrogen contents caused a greatly increased susceptibility to time-dependent fracture. (auth)
Date: October 10, 1962
Creator: Weinstein, D. & Holtz, F. C.
Object Type: Report
System: The UNT Digital Library
REACTIVITY CALIBRATIONS AND FISSION-RATE DISTRIBUTIONS IN AN UNMODERATED, UNREFLECTED URANIUM-MOLYBDENUM ALLOY RESEARCH PROGRAM (open access)

REACTIVITY CALIBRATIONS AND FISSION-RATE DISTRIBUTIONS IN AN UNMODERATED, UNREFLECTED URANIUM-MOLYBDENUM ALLOY RESEARCH PROGRAM

Completion of zero-power critical experiments with the ORNL Health Physics Research Reactor is reported. A description is given concerning these experiments which were used to determine the critical size, fission-rate distributions, reactivity calibrations of its movable parts, the temperature coefficient of reactivity, and the reactivity effects of the presence of neutron- reflecting materials adjacent to the reactor. (J.R.D.)
Date: May 10, 1962
Creator: Mihalczo, J.T.
Object Type: Report
System: The UNT Digital Library
Petroleum marketing monthly, October 1991. [Contains glossary] (open access)

Petroleum marketing monthly, October 1991. [Contains glossary]

This report is designed to give information and statistical data about a variety of crude oils and refined petroleum products. The publication provides statistics on crude oil costs and refined petroleum products sales for use by industry, government, private sector analysts, educational institutions, and consumers. Data on crude oil include the domestic first purchase price, the f.o.b. and landed cost of imported crude oil, and the refiner's acquisition cost of crude oil. Sales data for motor gasoline, distillates, residuals, aviation fuels, kerosene, and propane are presented. 12 figs., 55 tabs.
Date: October 10, 1991
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Kilowatt Isotope Power System: component test report for the ground demonstration system accumulator. 77-KIPS-100 (open access)

Kilowatt Isotope Power System: component test report for the ground demonstration system accumulator. 77-KIPS-100

The purpose of this test was to demonstrate that the system accumulator for the developmental program to be conducted on the Kilowatt Isotope Power System (KIPS) fulfilled the requirements of the test procedure (TP 400) test objectives. The results of the expulsion testing performed on the system accumulator are presented.
Date: October 10, 1977
Creator: Brainard, E.L.
Object Type: Report
System: The UNT Digital Library
LOADING AND ELUTION CHARACTERISTICS OF SOME NATURAL AND SYNTHETIC ZEOLITES (open access)

LOADING AND ELUTION CHARACTERISTICS OF SOME NATURAL AND SYNTHETIC ZEOLITES

The cation exchange characteristics of several commercially available zeolites were evaluated, Equilibrium loading characteristics and exchange capacities were determined experimentally in the binary systems cesium-lithium, cesium-- sodium, cesium--potassium, cesium-Tubidium, cesium -- hydrogen, cesium-- ammonium, strontium-- magnesium, strontium-- calcium, strontium-- barium, and strontium-- hydrogen for several zeolites. Exchangeable cation fractions in the equilibrium solutions were varied from 0.2 to 0.00001, while the total normality of the system constituents was held constant. Results were plotted as equivalent fraction of the traced cation on the zeolite at equilibrium vs. the fraction of traced cation remaining in the equilibrium solution. If an influent composition is known, and falls in the system listed above, zeolite column loading may be read directly in univalent-univalent or divalent-divalent systems. However, in the strontium-sodium or strontium-- hydrogen systems, a k value must be used because squared terms appear in the equilibrium expression as follows: 2 Na- zeolite plus or minus Sr-solution in equilibrium 2 Nasolution + Sr-zeolite, or k = (Sr-zeolite)(Na-solution)/ (Na-zeolite)2(Sr-solution). The k for a given cation is a function of zeolite loading with that cation. Several column 50% loading capacities were determined to randomly test the validity of the above curves to predict column capacities, Several columns …
Date: August 10, 1962
Creator: Ames, L.L. Jr. & Knoll, K.C.
Object Type: Report
System: The UNT Digital Library
Quarterly Technical Report on Spert Project, January-March 1962 (open access)

Quarterly Technical Report on Spert Project, January-March 1962

None
Date: August 10, 1962
Creator: Schroeder, F.
Object Type: Report
System: The UNT Digital Library
RLPORINC: the RELAP4/MOD5 interface to ORINC (open access)

RLPORINC: the RELAP4/MOD5 interface to ORINC

The Oak Ridge Inverse code, ORINC, calculates the temperature distribution in an electric core pin from internal temperatures and the conditions in the surrounding environment. While the internal temperatures can be obtained from thermocouples in the Thermal Hydraulic Test Facility, the needed environmental conditions cannot be determined as directly from experimental data. However, this information can be determined from a modified version of the Reactor Linearized Analysis Program, RELAP. In particular, the IBM form of RELAP/MOD5 UPDATE2, as released by the Idaho National Engineering Laboratory, was modified to save the proper information in a convenient format. This document describes this RELAP-to-ORINC interface version of RELAP4 which has been named RLPORINC.
Date: January 10, 1978
Creator: Cliff, S.B.
Object Type: Report
System: The UNT Digital Library
System for producing a uniform rubble bed for in-situ processes (open access)

System for producing a uniform rubble bed for in-situ processes

A method and a cutter are disclosed for producing a large cavity filled with a uniform bed of rubblized oil shale or other material, for in-situ processing. A raise drill head has a hollow body with a generally circular base and sloping upper surface. A hollow shaft extends from the hollow body. Cutter teeth are mounted on the upper surface of the body and relatively small holes are formed in the body between the cutter teeth. Relatively large peripheral flutes around the body allow material to drop below the drill head. A pilot hole is drilled into the oil shale deposit. The pilot hole is reamed into a large diameter hole by means of a large diameter raise drill head or cutter to produce a cavity filled with rubble. A flushing fluid, such as air, is circulated through the pilot hole during the reaming operation to remove fines through the raise drill, thereby removing sufficient material to create sufficient void space, and allowing the larger particles to fill the cavity and provide a uniform bed of rubblized oil shale.
Date: April 10, 1981
Creator: Galloway, Terry R.
Object Type: Patent
System: The UNT Digital Library
Upgrade of the Proton West secondary beamline (open access)

Upgrade of the Proton West secondary beamline

As originally designed and operated, protons entering PW6 were steered by a series of EPB dipoles into a single interaction length beryllium target, some 43 feet from the enclosure wall. Ensuing secondary beams, either p{sup +}/{pi}{sup +} or p{sup -}/{pi}{sup -}, were collected by a string of quadrupoles following the target, steered westward, away from the Proton Center line, through PW6 and PW7, and ultimately focussed on experiment production targets located within the large PW8 hall. Around the Spring of 1988 it was decided to upgrade the existing Proton West secondary beamline to allow for transport of a primary proton beam, anticipated to be either 800 or 900 GeV/c, through PW8. This upgrade project, which is now nearing completion, was largely motivated by the then recent approval of E-771, a hadronic beauty production experiment located in PW8. E-771 represents the third in a series of experiments for the large-acceptance dimuon spectrometer presently located at the end of the Proton West beamline. This Technical Memo is a summary of the upgrade --- an explanation of the underlying strategy and a documentation of the final locations of the secondary beamline elements. 6 refs., 2 figs., 2 tabs.
Date: October 10, 1989
Creator: Spiegel, L.
Object Type: Report
System: The UNT Digital Library
Analytical model for the dynamic resistivity of electrically-exploded conductors (open access)

Analytical model for the dynamic resistivity of electrically-exploded conductors

A detailed model for the dynamic resistivity of an exploding conductor presents many difficulties. An electrically-exploded conductor undergoes significant hydrodynamic expansion as it is heated. Resistivity is a function of both the temperature and density of a conductor and realistic models for resistivity over the range of parameter space experienced by an exploding conductor are quite complex. See for example, the model of Lee and More (1984). Calculation of the hydrodynamic expansion of the conductor during and subsequent to the explosion is likewise dependent on detailed knowledge of the equation of state for the conductor in a range where few experimental data exist. A further complication is the strong magnetic field which couples the hydrodynamic expansion to the currents flowing in the expanding material. In spite of the difficulties, progress is being made on detailed modeling of fuses and exploding conductors (Lidemuth and co-workers, 1985). A simpler approach has proved to be quite useful for modeling the electrical behavior of exploding bridgewire and slapper detonators and for modeling the explosionss of large conductors exploded with large capacitor banks. In the work described here, a simple, empirical model was developed which can be expressed as a closed-form algebraic expression involving four …
Date: October 10, 1986
Creator: Lee, R. S.
Object Type: Article
System: The UNT Digital Library
TWO AUXILIARY CODES FOR USE WITH RENUPAK (open access)

TWO AUXILIARY CODES FOR USE WITH RENUPAK

Two IBM-7090 codes were written to aid the user of the neutron moments method code RENUPAK. One code computes and punches response function input cards for RENUPAK or NIOBE (another neutron transport code). The second code reads RENUPAK flux tapes and prints out a compact edit including dose rate as a function of distance. (auth)
Date: August 10, 1962
Creator: Trubey, D.K.
Object Type: Report
System: The UNT Digital Library
NEUTRON THERMALIZATION MEASUREMENTS USING AN ELECTRON LINEAR ACCELERATOR (open access)

NEUTRON THERMALIZATION MEASUREMENTS USING AN ELECTRON LINEAR ACCELERATOR

Discussions are presented concerning integral experiments primarily on water and graphite systems. A description of experimental facilities is included along with details of die-away experiments, infinite-medium spectrum measurements, spatially dependent spectrum measurements, spectrum measurements for graphite systems, and development of a subcritical assembly program. (J.R.D.)
Date: April 10, 1962
Creator: Beyster, J R
Object Type: Report
System: The UNT Digital Library
Heavy recycle solvent studies in two-stage coal liquefaction. Final technical report, September 1, 1982-December 30, 1983 (open access)

Heavy recycle solvent studies in two-stage coal liquefaction. Final technical report, September 1, 1982-December 30, 1983

The objective of this program has been to study the chemistry of the components with high boiling points in a direct coal liquefaction recycle solvent and to identify those components which lead to higher overall yields and improved product stability in the initial coal dissolution step of direct coal liquefaction processes. The major conclusions are: -454 C recycle solvent is primarily aromatic hydrocarbons (73%) and contains almost no asphaltenes; +454 C recycle solvent is primarily asphaltenes and aromatic hydrocarbons; recycle solvent also contains aliphatic hydrocarbons, N-containing aromatics and O-containing aromatics; heteroatoms in coal derived materials seem to be grouped by type, i.e. acidic O and basic N and sulfur occur together; under helium a small net amount of hydrogen and more CO and CO/sub 2/ are produced than under hydrogen; under hydrogen the amounts of H/sub 2/S and hydrocarbon gases are increased and a small amount of hydrogen gas is usually consumed; overall coal conversions to THF solubles are improved by adding more -454 C solvent but decreased by adding +454 C solvent; for added fractions of -454 C solvent the pecent conversion to THF solubles increases in the order aromatic hydrocarbons (+7.2) > aliphatic hydrocarbons (+0.8) > no added …
Date: January 10, 1984
Creator: Longanbach, J. R.
Object Type: Report
System: The UNT Digital Library
Dosimetry measurements external to a 10 kiloliter liquid-air vessel containing a D-T neutron source. [14 MeV neutrons] (open access)

Dosimetry measurements external to a 10 kiloliter liquid-air vessel containing a D-T neutron source. [14 MeV neutrons]

To determine the radiation attenuation characteristics of liquid air (109 g/cm/sup 2/ thick) for 14 MeV neutrons from a central D-T source in a 10 kL vessel, radiation dose measurements were made using a large tissue-equivalent ion chamber external to the vessel. The shielding characteristics of steel spherical shells were also investigated. Experimental results were analyzed and compared with TARTNP Monte Carlo code calculations. Degradation of the ion chamber's response to high-energy neutrons was established and incorporated into the analysis. The dose attenuation factor for the unshielded detector was measured to be 0.073, compared with the calculated value of 0.081. The shielded detector signals were reduced only modestly; with a 10-cm-thick shell, the signal from the filled vessel dropped twofold.
Date: October 10, 1977
Creator: Tripler, D. J.; Goldberg, E. & Farley, W. E.
Object Type: Report
System: The UNT Digital Library
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