Serial/Series Title
Data Summary of Municipal Solid Waste Management Alternatives
23
Winter Fuels Report
17
Fiscal Year 1996
7
Fiscal Year 2007
7
Fiscal Year 1998
6
Hanford Laboratories Operation Monthly Activities Report
6
LWBR Development Program
6
Chemical Processing Department Monthly Report
5
Fiscal Year 1997
5
Fiscal Year 1999
5
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25,501 Matching Results
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25,489 - 25,501 of
25,501
Zirconia-Based Mixed Potential CO/HC Sensors with LaMnO3 and Th-doped YSZ Electrodes
Abstract: We have investigated the performance of dual metal oxide electrode mixed potential sensors in an engine-out, dynamometer environment. Sensors were fabricated by sputtering thin films of LaMnO{sub 3} and Tb-doped YSZ onto YSZ electrolyte. Au gauze held onto the metal oxide thin films with Au ink was used for current collection. The exhaust gas from a 4.8L, V8 engine operated in open loop, steady-state mode around stoichiometry at 1500 RPM and 50 Nm. The sensor showed a stable EMF response (with no hysteresis) to varying concentrations of total exhaust gas HC content. The sensor response was measured at 620 and 670 C and shows temperature behavior characteristic of mixed potential-type sensors. The results of these engine-dynamometer tests are encouraging; however, the limitations associated with Au current collection present the biggest impediment to automotive use.
Date:
October 1, 2000
Creator:
Brosha, Eric L.; Mukundan, Rangachary; Brown, David R.; Garzon, Fernando H.; Visser, J. H.; Thompson, David J. et al.
Object Type:
Article
System:
The UNT Digital Library
Zirconia-foil compatibility test. Phase I. [Thermal insulation for Brayton isotope power system (BIPS)]
The objective of the tests was to characterize the compatibility of zirconia powder with candidate foil materials for application to the Brayton Isotope Power System (BIPS). Recent MULTI-FOIL meltdown experiments and compatibility tests indicate that the current foil material choices for the BIPS should be reconsidered. Specifically, the items of concern are: (1) higher than anticipated rate of nickel vaporization, (2) compatibility of the zirconia coating with nickel above 600/sup 0/C, and (3) compatibility of the zirconia coating with columbium at temperatures up to 950/sup 0/C. Chemical interaction between the zirconia coating and the substrate foil would degrade the insulation characteristics of the MULTI-FOIL. The tests investigated the compatibilities of zirconia coatings with nickel, niobium, molybdenum and oxidized nickel foils. The data from these compatibility tests provide additional information for system modification.
Date:
October 1, 1976
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Zirconium metal-water oxidation kinetics. III. Oxygen diffusion in oxide and alpha Zircaloy phases. [BWR; PWR]
The reaction of Zircaloy in steam at elevated temperature involves the growth of discrete layers of oxide and oxygen-rich alpha Zircaloy from the parent beta phase. The multiphase, moving boundary diffusion problem involved is encountered in a number of important reaction schemes in addition to that of Zircaloy-oxygen and can be completely (albeitly ideally) characterized through an appropriate model in terms of oxygen diffusion coefficients and equilibrium concentrations for the various phases. Conversely, kinetic data for phase growth and total oxygen consumption rates can be used to compute diffusion coefficients. Equations are developed that express the oxygen diffusion coefficients in the oxide and alpha phases in terms of the reaction rate constants and equilibrium solubility values. These equations were applied to recent experimental kinetic data on the steam oxidation of Zircaloy-4 to determine the effective oxygen diffusion coefficients in these phases over the temperature range 1000--1500/sup 0/C.
Date:
October 1, 1976
Creator:
Pawel, R. E.
Object Type:
Report
System:
The UNT Digital Library
ZIRCONIUM PROCESSING CAPABILITY OF THE IDAHO CHEMICAL PROCESSING PLANT
None
Date:
October 1, 1964
Creator:
Bower, J.R.
Object Type:
Report
System:
The UNT Digital Library
ZIRCONIUM RESEARCH AND DEVELOPMENT. Progress Report No. 9 for September 15, 1950 to October 15, 1950
A zirconium crystal bar, weighing 29 pounds and 1 5/16 inches in diameter by 8 feet in over-all length, was prepared, using pear-shaped zirconium couples to join the filament to the electrodes. This crystal bar was the largest produced to date in the 16-in.-diam. de Boer unit. The design of the couplings was modified to incorporate improvements indicated by the initial run, and another run is in progress. Binary alloys of Zr and Ni, Cr, and Si, as well as a zirconium alloy containing Fe, Al, and Si, were prepared for use as feed material in the small pyrex de Boer bulbs. The transfer of these elements from the feed to the crystal bar is being investigated. The rate of deposition and the type of crystal structure obtained with additions of various amounts of iodine are being studied. (auth)
Date:
October 15, 1950
Creator:
Bulkowski, H.H.; Sebenick, J.J.; Campbell, I.E. & Gonser, B.W.
Object Type:
Report
System:
The UNT Digital Library
The Zirflex Process
tive dissolution of zirconium or Zircaloy fuel cladding. The process involves the dissolution of the cladding material in solutions of ammonium fluoride alone or in mixture with amonium nitrate. Mixtures of amonium fluoride and amonium nitrate are preferred since they result in very little evolution of hydrogen during the is that these solutions attack austenitic stainless steels only slowly, in sharp contrast to the media (e.g., hydrofluoric acid or hydrofluoric-nitric acid mixtures) generng 6 M NH/sub 4/F, the rate of pentration of Zircaloy-2 is nearly 100 mils/hr, while that of typical austentic stainless steels is only about 0.5 mil/month. (auth)
Date:
October 31, 1958
Creator:
Swanson, J. L.
Object Type:
Report
System:
The UNT Digital Library
Zn-Site Determination in Protein Encapsulated ZnxFe3-xO4 Nanoparticles
The X-ray absorption spectra of the Fe and Zn L-edges for 6.7 nm Fe{sub 3}O{sub 4} nanoparticles grown inside 12 nm ferritin protein cages with 10%, 15%, 20% and 33% zinc doping, shows that the Zn is substitutional as Zn{sup 2+} within the iron oxide host structure. A Neel-Arrhenius plot of the blocking temperature in the frequency dependent ac-susceptibility measurements show that the particles are non-interacting and that the anisotropy energy barrier is reduced with Zn loading. X-ray magnetic circular dichroism (XMCD) of the Fe displays a linear decrease with Zn-doping in sharp contrast to the initial increase present in the bulk system. The most plausible explanation for the moment decrease is that Zn substitutes preferentially into the tetrahedral A-site as a Zn{sup 2+} cation, generating a mixed spinel.
Date:
October 1, 2008
Creator:
Pool, V. L.; Klem, M. T.; Holroyd, J.; Harris, T.; Arenholz, E.; Young, M. et al.
Object Type:
Article
System:
The UNT Digital Library
Zonal Flow Measurements Concept I
We study the characteristics of self-generated zonal flows as observed in nonlinear global gyrokinetic simulations of toroidal ITG turbulence for typical parameters of DIII-D core plasmas, and discuss various possibilities for experimental measurements and the development of new diagnostics.
Date:
October 1, 1999
Creator:
Synakowski, E.J.; Burrell, K.H.; Nazikian, R.; Hahm, T.S. & Lin, Z.
Object Type:
Report
System:
The UNT Digital Library
Zone of Interaction Between Hanford Site Groundwater and Adjacent Columbia River
This report describes the FY 2000 results of a Science and Technology investigation of the groundwater/river interface at the Hanford Site. The investigation focused on (1) a 2-D simulation of water flowpaths beneath the shoreline region under the influence of a transient river stage, and (2) mixing between groundwater and river water.
Date:
October 23, 2001
Creator:
Peterson, Robert E. & Connelly, Michael P.
Object Type:
Report
System:
The UNT Digital Library
Zone of Interaction Between Hanford Site Groundwater and Adjacent Columbia River
This report describes the FY 2000 results of a Science and Technology investigation of the groundwater/river interface at the Hanford Site. The investigation focused on (1) a 2-D simulation of water flowpaths beneath the shoreline region under the influence of a transient river stage, and (2) mixing between groundwater and river water.
Date:
October 23, 2001
Creator:
Peterson, Robert E.
Object Type:
Report
System:
The UNT Digital Library
Zone refining high-purity germanium
The effects of various parameters on germanium purification by zone refining have been examined. These parameters include the germanium container and container coatings, ambient gas and other operating conditions. Four methods of refining are presented which reproducibly yield 3.5 kg germanium ingots from which high purity (vertical barN/sub A/ - N/sub D/vertical bar less than or equal to2 x 10/sup 10/ cm/sup -3/) single crystals can be grown. A qualitative model involving binary and ternary complexes of Si, O, B, and Al is shown to account for the behavior of impurities at these low concentrations.
Date:
October 1, 1977
Creator:
Hubbard, G. S.; Haller, E. E. & Hansen, W. L.
Object Type:
Article
System:
The UNT Digital Library
zPicture: Dynamic Alignment and Visualization Tool for Analyzing Conservation Profiles
None
Date:
October 27, 2003
Creator:
Ovcharenko, I; Loots, G G; Hardison, R C; Miller, W; Stubbs, L; Paar, H et al.
Object Type:
Article
System:
The UNT Digital Library
ZPR-6 Assembly 7 High {Sup 240} Pu Core : A Cylindrical Assemby With Mixed (Pu, U)-Oxide Fuel and a Central High {Sup 240} Pu Zone.
Over a period of 30 years more than a hundred Zero Power Reactor (ZPR) critical assemblies were constructed at Argonne National Laboratory. The ZPR facilities, ZPR-3, ZPR-6, ZPR-9 and ZPPR, were all fast critical assembly facilities. The ZPR critical assemblies were constructed to support fast reactor development, but data from some of these assemblies are also well suited to form the basis for criticality safety benchmarks. Of the three classes of ZPR assemblies, engineering mockups, engineering benchmarks and physics benchmarks, the last group tends to be most useful for criticality safety. Because physics benchmarks were designed to test fast reactor physics data and methods, they were as simple as possible in geometry and composition. The principal fissile species was {sup 235}U or {sup 239}Pu. Fuel enrichments ranged from 9% to 95%. Often there were only one or two main core diluent materials, such as aluminum, graphite, iron, sodium or stainless steel. The cores were reflected (and insulated from room return effects) by one or two layers of materials such as depleted uranium, lead or stainless steel. Despite their more complex nature, a small number of assemblies from the other two classes would make useful criticality safety benchmarks because they have …
Date:
October 1, 2007
Creator:
Lell, R. M.; Schaefer, R. W.; McKnight, R. D.; Tsiboulia, A.; Rozhikhin, Y.; Division, Nuclear Engineering et al.
Object Type:
Report
System:
The UNT Digital Library