NQR-NMR studies of higher alcohol synthesis Cu-Co catalysts (open access)

NQR-NMR studies of higher alcohol synthesis Cu-Co catalysts

Copper and cobalt are the key elements in syngas conversion catalyst systems used for higher alcohol synthesis. Their proximity and synergy sensitively control the selectivity and efficiency of the process. It is believed that their outer electronic charge distribution which is responsible for their electrical and magnetic properties might be governing their catalytic properties also. To examine the correlation between catalytic and magnetic properties, a series of copper cobalt catalysts (Co/Cu ratio 5:1 to 5:5) with and without a support were prepared. The nuclear quadrupole resonance spectrum of copper and (zero-field) nuclear magnetic resonance spectrum of cobalt and magnetization and hysteresis character of the catalyst were analyzed. Similar to the catalytic results, the magnetic results also were found to be very sensitive to the preparation technique. The results indicate possible electron exchange between copper and cobalt, and cobalt and the support Titania.
Date: January 14, 1991
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Enhanced durability and reactivity for zinc ferrite desulfurization sorbent (open access)

Enhanced durability and reactivity for zinc ferrite desulfurization sorbent

AMAX Research Development Center (AMAX R D) has been investigating methods for enhancing the reactivity and durability of the zinc ferrite desulfurization sorbent. Zinc ferrite sorbents are intended for use in desulfurization of hot coal gas in integrated gasification combined cycle (IGCC) or molten carbonate fuel cell (MCFC) applications. For the present program, the reactivity of the sorbent may be defined as its sulfur sorption capacity at the breakthrough point and at saturation in a bench-scale, fixed-bed reactor. Durability may be defined as the ability of the sorbent to maintain important physical characteristics such As size, strength, and specific surface area during 10 cycles of sulfidation and oxidation.
Date: November 14, 1988
Creator: Jha, Mahesh C. & Berggren, Mark H.
Object Type: Report
System: The UNT Digital Library
LITERATURE SEARCH ON LEAD-BISMUTH ALLOYS (open access)

LITERATURE SEARCH ON LEAD-BISMUTH ALLOYS

BS>The use of a lead-bismuth alloy as a coolant in the removal of heat from power-generating nuclear reactors was considered with the possibility that its ternary alloy with uranium or plutonium might be of use in a reactor of the circulating-liquid-fuel type. Information collected from the literature covering phase-equilibrium studies, physicalproperty data, and reactivity of this alloy toward other substances is presented. (auth)
Date: February 14, 1950
Creator: Lee, M.E.
Object Type: Report
System: The UNT Digital Library
HIVELITE propellant characterization (open access)

HIVELITE propellant characterization

None
Date: March 14, 1975
Creator: Finger, M. & Hayes, B.
Object Type: Report
System: The UNT Digital Library
Programmable control system for scanning cylindrical parts (open access)

Programmable control system for scanning cylindrical parts

None
Date: March 14, 1975
Creator: Neal, R. E.
Object Type: Report
System: The UNT Digital Library
Eucalyptus plantations for energy production in Hawaii. Technical status report, October 1, 1978-June 30, 1980 (open access)

Eucalyptus plantations for energy production in Hawaii. Technical status report, October 1, 1978-June 30, 1980

Progress made on accomplishing research objectives is reported. The objectives of this project are: (1) to increase the biomass production of Eucalyptus; (2) to determine the optimum requirements to maximize yield; (3) to assess planting, cultivation, harvesting, and transportation equipment requirements; (4) to determine the optimum mixture of biomass (eucalyptus and bagasse) at the generator for the production of electricity; and (5) to evaluate a complete production/conversion system which utilized optimum management conditions in relationship to costs. (DMC)
Date: July 14, 1980
Creator: unknown
Object Type: Report
System: The UNT Digital Library
LITHIUM HYDRIDE PROPERTIES (open access)

LITHIUM HYDRIDE PROPERTIES

A tabulation is presented of values for selected properties of lithium hydride. (M.C.G.)
Date: March 14, 1961
Creator: Welch, F.H.
Object Type: Report
System: The UNT Digital Library
Interaction of xenon light with the surface of 304 stainless steel (open access)

Interaction of xenon light with the surface of 304 stainless steel

Laser amplifier frames fabricated from Type 304 stainless steel are known to cause damage to glass lenses by ejecting particles which are deposited on the lenses. High energy pulses of xenon light interact with the steel surface to produce damage sites. Heat treatment and surface cleaning procedures greatly affect the surface stability of the steel and influence contamination generated by the steel. It is believed that inclusions and/or carbides play a role, and the size of damage sites observed on glass correlate with the size of nonmetallic phases in the steel. Thermal etching of the steel was found to be a principle mechanism of surface damage caused by the high energy xenon light.
Date: February 14, 1978
Creator: Krenzer, R. W.
Object Type: Report
System: The UNT Digital Library
Study of the health effects of bicycling in an urban atmosphere. Final report (open access)

Study of the health effects of bicycling in an urban atmosphere. Final report

This report analyzes data on the health effects of bicycling in an urban environment through intensive study of ten healthy male subjects bicycling or driving in systematically varied conditions in the streets of Washington, D.C. Evaluation criteria for available technology and instrumentation are included and a methodology is developed for route selection. Specific air pollutants (carbon monoxide, ozone, sulfates, nitrates, and particulates) are measured concurrently with exposure and subsequent changes in health status identified through pulmonary function testing, cardiovascular testing, and blood and symptoms analysis. The report concludes that no major adverse short-term health effects were noted for ten healthy male subjects while bicycling or driving in levels of pollution and thermal stress encountered during the study period. Recommendations for further research are also presented.
Date: October 14, 1977
Creator: Waldman, M.; Weiss, S. & Articola, W.
Object Type: Report
System: The UNT Digital Library
Considerations of bunch-spacing options for multi-bunch operation of the Tevatron Collider (open access)

Considerations of bunch-spacing options for multi-bunch operation of the Tevatron Collider

This discussion will consider a number of points relevant to limitations, advantages and disadvantages of various arrangements of bunches in the Tevatron proton-antiproton collider. The considerations discussed here will be limited to: (a) bunch spacing symmetry and relation to the relative luminosity at B0 and D0 and the beam-beam interaction with separated beams; (b) bunch spacing constraints imposed by Main Ring RF coalescing and the optics of beam separation at B0 and D0; and (c) bunch spacing constraints imposed by injection and abort kicker timing requirements, and by the Antiproton Source RF unstacking process. 20 figs., 17 tabs.
Date: December 14, 1989
Creator: Dugan, G.
Object Type: Report
System: The UNT Digital Library
Creep Rupture in the Presence of a Fast Neutron Flux (open access)

Creep Rupture in the Presence of a Fast Neutron Flux

Possible mechanisms for creep rupture during irradiation are examined. Evidence that the rupture occurs by grain boundary sliding alone, or by vacancy condensation, is compared. It is observed that vacancy condensation is the more probable mechanism, and that this mechanism predicts a reduction in creep rupture life for metals exposed to a fast neutron flux (neglecting effects of radiation annealing). (T.F.H.)
Date: January 14, 1959
Creator: Gregory, D. P.
Object Type: Report
System: The UNT Digital Library
A sendmail. cf scheme for a large network (open access)

A sendmail. cf scheme for a large network

Like most large networked sites our users depend heavily on the electronic mail system for both internal and off-site communications. Unfortunately the sendmail.cf file, which is used to control the behavior of the sendmail program, is somewhat cryptic and difficult to decipher for the neophyte. So, on one hand you have a highly visible, frequently used utility, and on the other hand a not-so-easily acquired system administration forte. Here is the sendmail topology of our site, what premises we based it on, and the parts of the sendmail.cf files which support the topology.
Date: August 14, 1991
Creator: Darmohray, T.M.
Object Type: Article
System: The UNT Digital Library
LLL Geothermal Energy Development Program. Status Report, January 1974--January 1975. [Impulse Turbines, Total Flow Conversion Systems] (open access)

LLL Geothermal Energy Development Program. Status Report, January 1974--January 1975. [Impulse Turbines, Total Flow Conversion Systems]

None
Date: February 14, 1975
Creator: Austin, A. L.
Object Type: Report
System: The UNT Digital Library
NQR-NMR studies of higher alcohol synthesis Cu-Co catalysts (open access)

NQR-NMR studies of higher alcohol synthesis Cu-Co catalysts

The primary objective of the project is to examine the relations between the catalytic and magnetic properties of the copper-cobalt higher alcohol synthesis catalysts. We have undertaken to investigate the magnetic character by studying the Nuclear Quadrupole resonance of copper and (Zerofield) Nuclear Magnetic Resonance of cobalt in copper cobalt catalysts.
Date: January 14, 1992
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Reactor containment analysis for BWR suppression systems. Progress report, April--October 1977 (open access)

Reactor containment analysis for BWR suppression systems. Progress report, April--October 1977

Work during the period included analytic studies of vent clearing and jet-slug dynamics and computer simulations (HEMP and CHAMP codes) of pressure suppression experiments.
Date: December 14, 1977
Creator: Edwards, L.L.
Object Type: Report
System: The UNT Digital Library
REMOTE DISSOLUTION AND ANALYTICAL PROGRAM FOR IRRADIATED THORIUM (open access)

REMOTE DISSOLUTION AND ANALYTICAL PROGRAM FOR IRRADIATED THORIUM

A remote dissolution and analytical program for irradiated thorium is given. The aluminum jacket on the slug was dissolved with 6M nitric acid and 0.005M mercuric nitrate. After a water wash, the thorium dissolution was accomplished with concentrated nitric acid made 0.04M in hydrofluoric acid. Weighing, dissolving, and sampling were done remotely in the multicurie cell at the Idaho Chemical Processing Plant. Handling techniques for weighing and dissolving the slugs are described. Transferring and sampling apparatus as well as sampling techniques for the dissolved material are discussed. Analytical data obtained are tabulated. Abstracts of analytical methods for uranium concentration and isotope ratio, aluminum, thorium, cesium, and cerium are given. (auth)
Date: July 14, 1961
Creator: Huff, G. A.; Doggett, I. L.; Fletcher, R. D. & Jacobson, M. E.
Object Type: Report
System: The UNT Digital Library
Analysis of LOFT steam generator main feed piping loop seal modification (open access)

Analysis of LOFT steam generator main feed piping loop seal modification

The stress analysis is presented for the proposed loop seal modification to the LOFT Steam Generator Main Feed Piping. THE SAP IV finite element computer program was used to analyze normal, upset, emergency, and faulted conditions. Results of the analysis indicate that the modified main feed piping system will satisfy all structural adequacy criteria specified in Subarticle NC-3650 of the ASME Boiler and Pressure Vessel Code. Results also show that the isolation snubber configuration, specified in LTR 115-11, will also be adequate for the piping configuration analyzed.
Date: February 14, 1978
Creator: Nitzel, M.E.
Object Type: Report
System: The UNT Digital Library
ORNL PROCEDURES FOR CONTROLLED-POTENTIAL COULOMETRIC TITRATION OF PLUTONIUM (open access)

ORNL PROCEDURES FOR CONTROLLED-POTENTIAL COULOMETRIC TITRATION OF PLUTONIUM

Six procedures, in stepwise form, that can be used for the determination of plutonium in several forms by controlled-potential coulometric titration are presented. (auth)
Date: September 14, 1962
Creator: Shults, W.D.
Object Type: Report
System: The UNT Digital Library
Analysis of potential nonelectrical applications of geothermal energy and their place in the national economy (open access)

Analysis of potential nonelectrical applications of geothermal energy and their place in the national economy

None
Date: February 14, 1975
Creator: Reistad, G.M.
Object Type: Report
System: The UNT Digital Library
HOT CELL DEMONSTRATION OF ZIRFLEX AND SULFEX PROCESSES. Report No. 3 (open access)

HOT CELL DEMONSTRATION OF ZIRFLEX AND SULFEX PROCESSES. Report No. 3

ABS>Hot cell demonstration of the Zirflex decladding process coupled with a modified Purex solvent extraction process was completed using specimens of Zircaloy-clad UO/sub 2/ irradiated to levels of 6150-14,600 Mwd/TU. Soluble losses of uranium and plutonium to the decladding solutions were about 0.05%. Centrifugation of the decladding solution is probably necessary to remove up to 1% of the UO/sub 2/ present as fines resulting from the fracture of low (93 to 95%) density pellets; high (96%) density pellets produced few fines. Approximately 5 hours were required to dissolve the UO/sub 2/ core material (14,000 Mwd/TU) in 4M HNO/sub 3/ versus 6 to 7 hours for unirradiated pellets to produce a solvent extraction feed of 100 g U/l and 3M HNO/sub 3/. Gamma decontamination factors for uranium in the Purex CU stream and plutonium in the BP stream were increased by factors of 2 to 10 from the normal 1.3 x 10/sup 3/ and 2.1 x 10/sup 3/, respectively, by pretreatment of the solvent extraction feed with dincetyl monoxime or its degradation product, oxalic acid. Preliminary data indicate radiation damage degrades the solvent, 30% TBP diluted with Amsco 125- 82, upon one pass through the mixer-settler banks with feed solutions irradiated …
Date: May 14, 1962
Creator: Goode, J.H. & Baillie, M.G.
Object Type: Report
System: The UNT Digital Library
Effect of salinity on geothermal well performance (open access)

Effect of salinity on geothermal well performance

None
Date: May 14, 1975
Creator: Grens, J.Z.
Object Type: Report
System: The UNT Digital Library
Kilowatt Isotope Power System: component test procedure for the ground demonstration system jet condenser focusing. 77-KIPS-59. Revision A (open access)

Kilowatt Isotope Power System: component test procedure for the ground demonstration system jet condenser focusing. 77-KIPS-59. Revision A

This test procedure (No. 404A) provides a detailed description of the verification methods which shall be used in the development program to be conducted on the Kilowatt Isotope Power System (KIPS) Jet Condenser to fulfill the requirements of the Ground Demonstration Test Plan, Section 6.4. This is a revision of Test Procedure No. 404.
Date: March 14, 1978
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Molecular biological enhancement of coal biodesulfurization. [Rhodococcus, thiobacillus] (open access)

Molecular biological enhancement of coal biodesulfurization. [Rhodococcus, thiobacillus]

The objective of this project is to produce one or more microorganisms capable of removing the organic and inorganic sulfur in coal. The original specific technical objectives of the project were to: clone and characterize the genes encoding the enzymes of the 4S'' pathway (sulfoxide/sulfone/sulfonate/sulfate) for release of organic sulfur from coal; return multiple copies of genes to the original host to enhance the biodesulfurization activity of that organism; transfer this pathway into a fast-growing chemolithotropic bacterium; conduct a batch-mode optimization/analysis of scale-up variables.
Date: June 14, 1990
Creator: Litchfield, J. H.; Fry, I.; Wyza, R. E.; Palmer, D. T.; Zupancic, T. J. & Conkle, H. N.
Object Type: Report
System: The UNT Digital Library
DISSOLUTION OF BeO-AND Al$sub 2$O$sub 3$-BASE REACTOR FUEL ELEMENTS. PART I (open access)

DISSOLUTION OF BeO-AND Al$sub 2$O$sub 3$-BASE REACTOR FUEL ELEMENTS. PART I

Aqueous methods for recovering uranium from BeO- and Al/sub 2/O/sub 3/- base gas-cooled-reactor fuel elements are being evaluated. Two methods for processing Hastelloy-X--clad pelletized BeO-base fuels containing 60 to 70% UO/ sub 2/, such as the GCRE and MGCR, seem feasible. One method involves mechanical stripping or chopping of the cladding followed by leaching of the uranium from the fuel pellets with boiling 6-l3M HNO/sub 3/. In the other method the cladding and UO/sub 2/ are dissolved in boiling 2M HNO/sub 3/-4M HCl. In either case, most of the BeO matrix remains as an undissolved residue. Pellets containing 70% UO/sub 3/ dissolved completely in less than 20 hr in boiling 8M HNO/sub 3/ containing either 2M H/sub 2/SO/sub 4/ or 0.5M HF, producing solutions containing 4 g of uranium per liter. Fuels of high BeO content, e.g. BeO--5% UO/sub 2/, dissolved only slowly in boiling aqueous reagents. Highest initial rates were in sulfuric acid solutions, log (Rate, mg min/sup -1/cm/sup -2/) = 0.223 (H/sub 2/SO/ sub 4, M) - 2.8l and in HF--NH/sub 4/F solutions. ln boiling 5-8M NH/sub 4/F the initial dissolution rate increased from 0.07 to 3.5 mg min/sup -1/cm/sup -2/ as the HF concentration increased from 0 …
Date: February 14, 1962
Creator: Warren, K S; Ferris, L M & Kibbey, A H
Object Type: Report
System: The UNT Digital Library