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Electrofuels Program
8
Field Demonstration of a Membrane Process to Separate Nitrogen From Natural Gas Progress Report
6
Winter Fuels Report
4
ARM Facilities Newsletter
3
BEEST Program
3
Fiscal Year 2000
3
Fiscal Year 2005
3
Fiscal Year 2007
3
Petroleum Marketing Monthly
3
Establishment of an Industry-Driven Consortium Focused on Improving the Production Performance of Domestic Stripper Wells Quarterly Report
2
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3,859 Matching Results
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A Bench-Scale Natural-Recirculation Dissolver
A natural-recirculation dissolver closely approaching a stirred-tank reactor in behavior was developed, and its feasibility was demonstrated in the mercury-catalyzed dissolution of aluminum in nitric acid, It was designed to utilize the heat of reaction and evolution of gaseous reaction products for recirculation and mixing. The dissolvent was 5-molar nitric acid, containing mercury in concentrations from 10/sup -4/ to 10/sup -3/ molar as a catalyst. Dissolution rates for 1/7 scale, simulated MTR fuel elements of 2-S aluminum ranged from 0.25 to 4.0 mg/(cm/sup 2/)(rain), depending on the catalyst concentration in the dissolvent and the dissolvent flow rate. For comparable catalyst and acid feed concentrations, dissolution rates, based on unit net superficial velocities, were nearly 25 times those for dissolution of randomly- packed flat plates in a pilot plant, continuous, flooded dissolver. (auth)
Date:
January 10, 1962
Creator:
Erickson, E. E.
Object Type:
Report
System:
The UNT Digital Library
Pressure limits of negative ion sources based upon gas efficiency and extracted ion-current density
The nature of the electrical discharge has an obvious impact upon the gas efficiency of an ion source and on the current density whch can be drawn from it. However external factors, such as the conductance of the grids and the background pressure along the beamline, also have an effect. Simple approximations based upon these factors show that there is a lower limit to the pressure of an ion source, which can deliver an ion beam of given current density at a specific gas efficiency. Estimates of ion stripping losses in a double gridded structure show that for all practical purposes, there is an upper limit as well.
Date:
March 10, 1982
Creator:
Fink, J.
Object Type:
Report
System:
The UNT Digital Library
Investigation into the repetition-rate limitations of magnetic switches
The use of magnetic switches to generate high power pulses has opened up a whole new spectrum of possibilities. Here we describe an investigation into the maximum repetition rates possible with these devices.
Date:
February 10, 1982
Creator:
Birx, D. L.; Reginato, L. L. & Schmidt, J. A.
Object Type:
Article
System:
The UNT Digital Library
SLAC Divertor Channel Entrance Thermal Stress Analysis
X-ray beams emerging from the new SLAC electron-positron storage ring (PEP) impinge on the entrance to tangential divertor channels causing highly localized heating in the channel structure. Analyses were completed to determine the temperatures and thermally-induced stresses due to this heating. These parts are cooled with water flowing axially over them at 30/sup 0/C. The current design and operating conditions should result in the entrance to the new divertor channel operating at a peak temperature of 123/sup 0/C with a peak thermal stress at 91% of yield. Any micro-cracks that form due to thermally-induced stresses should not propagate to the coolant wall nor form a path for the coolant to leak into the storage ring vacuum. 34 figs., 4 tabs.
Date:
July 10, 1985
Creator:
Johnson, Gary L.; Stein, Werner; Lu, Stephen C. & Riddle, Robert A.
Object Type:
Report
System:
The UNT Digital Library
Pilot demonstration: enhanced oil recovery by micellar-polymer waterflooding, Bell Creek field. Monthly technical progress report for October 1977
The work described covers the tasks for: Micellar-Polymer Systems Selection and Evaluation, Site Development, Pilot Performance Predictions, Fluid Distribution Facilities, and Log-Inject-Log Tests. (DLC)
Date:
November 10, 1977
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Importance of high order momentum terms in SLC optics
The evaluation of background levels at the SLC relies, in several cases, on the proper representation of how low momentum electrons propagate through the Arcs and the Final Focus System (FFS). For example, beam - gas bremsstrahlung in the arcs causes electrons of up to 6% energy loss to be transported through to the IP; secondary showers on edges of masks and collimators yield debris with a very wide momentum spectrum. This note is a naive attempt at checking the validity of TRANSPORT and TURTLE calculations, by evaluating the contributions of the momentum terms to increasingly higher order, and checking the mutual consistency of the results produced by the two methods on a beam of wide momentum spread. 8 refs., 4 figs., 1 tab.
Date:
July 10, 1985
Creator:
Kozanecki, W.
Object Type:
Report
System:
The UNT Digital Library
CATASTROPHIC OXIDATION OF HIGH-TEMPERATURE ALLOYS
The growth of nonprotective, crust-like oxide films was encountered in high-temperature alloy systems that contain molybdenum, vanadium, or tungsten as strengthening additions. The cause of accelerated oxidation in such alloys appears to be associated with the characteristically low melting temperatures of oxides of these refractory elements. The factors that contribute to a breakdown of oxidation protection in these systems are outlined and remedial methods which may be used to avoid catastrophic oxidation are discussed. Commonly encountered service failures that have resulted from catastrophic oxidation are also described. (auth)
Date:
November 10, 1961
Creator:
DeVan, J. H.
Object Type:
Report
System:
The UNT Digital Library
Energy generation in convective shells of low mass, low metallicity stars
We report on the non-negligible energy generation from the {sup 13}C neutron source and neutron capture reactions in low mass, low metallicity AGB stars. About 10{sup 4} L{sub {circle dot}} are generated within the thermal pulse convective shell by the combination of the {sup 13}C({alpha}, n){sup 16}O rate and the sum of the Y(Z,A)(n,{gamma})Y(Z,A + 1) reactions and beta decays. The inclusion of this energy source in an AGB thermal pulse evolution is shown to alter the evolution of the convective shell boundaries, and, hence, how the {sup 13}C is ingested into the convective shell. Also, the duration of the pulse itself is reduced by the additional energy input. The nucleosynthetic consequences are discussed for these evolutionary changes. 17 refs., 5 figs.
Date:
November 10, 1989
Creator:
Bazan, G. (Illinois Univ., Urbana, IL (USA). Dept. of Astronomy) & Lattanzio, J.C. (Lawrence Livermore National Lab., CA (USA))
Object Type:
Article
System:
The UNT Digital Library
NEUTRON FLUX AND Cd RATIO MEASUREMENTS IN THE HN-1 BEAM HOLE FOR THREE FUEL LOADINGS OF THE OAK RIDGE RESEARCH REACTOR
Neutron flux measurements were made in the Oak Ridge Research Reactor beam hole HN-l shield plug. at low reactor power (N/sub L/) with three fuel configurations. The purpose of these tests was to determine the most favorable fuel arrangement in the region of the experimental hole in order to permit minimization of exposure time of an in-pile slurry loop experiment using pure thoria. It was found that the perturbed thermal neutron flux decreased by factors of 2, each 1.4 in., at the forward end of the beam hole. Maximum and average fluxes observed for three fuel configurations were: high, 9.7 x l0/sup 13/ , 5.6 x 10/sup 13/; intermediate, 8.0 x 10/sup 13/, 4.7 x l0/sup 13/; and present operating, 7.4 x l0/sup 13/, 3.8 x 10/sup 13/. In the high and intermediate configurations fuel elements were located in the outer row of the lattice adjacent to the beam hole. Cadmium ratios were generally high (22 to 111) implying low available epi-cadmium flux under any of these configurations. (auth)
Date:
October 10, 1961
Creator:
Shor, A.J.f Mauney, T.H.
Object Type:
Report
System:
The UNT Digital Library
H-division quarterly report, October--December 1977. [Lawrence Livermore Laboratory]
The Theoretical EOS Group develops theoretical techniques for describing material properties under extreme conditions and constructs equation-of-state (EOS) tables for specific applications. Work this quarter concentrated on a Li equation of state, equation of state for equilibrium plasma, improved ion corrections to the Thomas--Fermi--Kirzhnitz theory, and theoretical estimates of high-pressure melting in metals. The Experimental Physics Group investigates properties of materials at extreme conditions of pressure and temperature, and develops new experimental techniques. Effort this quarter concerned the following: parabolic projectile distortion in the two-state light-gas gun, construction of a ballistic range for long-rod penetrators, thermodynamics and sound velocities in liquid metals, isobaric expansion measurements in Pt, and calculation of the velocity--mass profile of a jet produced by a shaped charge. Code development was concentrated on the PELE code, a multimaterial, multiphase, explicit finite-difference Eulerian code for pool suppression dynamics of a hypothetical loss-of-coolant accident in a nuclear reactor. Activities of the Fluid Dynamics Group were directed toward development of a code to compute the equations of state and transport properties of liquid metals (e.g. Li) and partially ionized dense plasmas, jet stability in the Li reactor system, and the study and problem application of fluid dynamic turbulence theory. 19 …
Date:
February 10, 1978
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Development of improved iron Fischer-Tropsch catalysts
The objective of proposed research is development of catalysts with enhanced slurry phase activity and better selectivity to fuel range products, through a more detailed understanding and systematic studies of the effects of pretreatment procedures and promoters/binders (silica) on catalyst performance.
Date:
January 10, 1992
Creator:
Bukur, D.B.
Object Type:
Report
System:
The UNT Digital Library
DISCUSSION OF AN ACTIVATION METHOD FOR MEASURING THE RATIO OF U$sup 238$ ABSORPTION TO U$sup 235$ FISSION IN A REACTOR
The theory is presented in detail of an activation method for measuring the ratio of U/sup 238/ absorptions to U/sup 235/ fissions in a nuclear reactor. The origin of the activities is discussed, the equations are given for interpretation of the measurements, and the expected counting rates are computed for a typical experiment in the EGCR. (auth)
Date:
August 10, 1962
Creator:
Preskitt, C.A.
Object Type:
Report
System:
The UNT Digital Library
PL-3 Project Quarterly Progress Report, January 1, 1962-March 31, 1962
Progress is reported on phase II in sections on final design, procurement, fabrication, testing, packaging, and crew training. A summary of completed phase I work on concept evaluation and preliminary design is also included. (J.R.D.)
Date:
April 10, 1962
Creator:
Humphries, G. E.
Object Type:
Report
System:
The UNT Digital Library
SUMMARY OF HRT RUN 21
The HRT was operated experimentally during run 2l at powers up to 5 Mw to explore the limiting conditions of fuel stability and to demonstrate the reliability of the system. The effect of core pressure on fuel stability was investigated over the range from l250 to 1750 psig. Stable operation at 5 Mw (2.6 Mw in the core) was demonstrated at 1250 psig. At 1600 and 1750 psig, fuel instability accompanied by rapid loss of reactivity occurred at powers down to 2.5 Mw. The threshold power for reactivity loss at intermediate pressures was raised by increasing the fuel acid/sulfate ratio from 0.28 to 0.34. In other studies the fuel temperature was varied from 240 to 275 deg C at sev eral different pressures. In some instances the reactor appeared more stable at the lower temperatures. The effects of suspended solids and oxygen concentration were examined briefly without conclusive results. At times during operation at low pressure and high power, an increase in reactivity, indicating deposition of uranium on the core tank, was observed. During an experiment to investigate this effect, a hole was melted in the core near the equator. The reactor was shut down for examination and modifications to …
Date:
October 10, 1961
Creator:
Haubenreich, P.N.; Bauman, H.F.; Bradley, N.C.; Engel, J.R.; Kolb, J.O.; Piper, H.B. et al.
Object Type:
Report
System:
The UNT Digital Library
Remote servicing features of two new mirror fusion reactors
Some general approaches to remote blanket change and servicing operations are briefly outlined for the LLL Field Reversed Mirror and Tandem Mirror Fusion reactors. Remote servicing system design requirements are briefly discussed. (RME)
Date:
June 10, 1977
Creator:
Neef, W.S.
Object Type:
Article
System:
The UNT Digital Library
Development of Liquid-Phase Sintering Techniques for Molybdenum Alloys. Final Report
An envelope-type microstructure produced by liquidphase sintering techniques was used to develop ductiIe molybdenum-base alloys for sodium-cooled fast reactor application. A total of 105 compositions was examined; 21 showed evidence of room-temperature ductility, and a number of other compositions appeared promising. The prerequisites for obtaining ductile liquid-phase sintered materials were demonstrated. The most ductile alloys produced are based on the Mo--Pd--Cu and Mo --W--Ni--Fe systems. Molybdenum-base compositions were developed which could be rolled to 90% reduction in thickness at room temperature. The compactibility of selected alloys with uranium at 750 deg C and liquid sodium at 650 deg C was studied. In both cases the presence of iron and nickel was found to be deleterious. Although alloys compatible with uranium were produced, the specimens exposed to liquid sodium all showed evidence of attack to varying degrees. Two compositions based on the Mo--W--Ni and W--Cr--Ni systems, respectively, appear to hold promise as potential canning materials for sodium- cooled fast reactor application. (auth)
Date:
November 10, 1960
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Longitudinal spin fluctuations in nickel
The longitudinal and transverse spin fluctuations in Ni have been measured below {Tc} by means of polarized neutron scattering in the momentum range 0.06 < q < 0.18 {angstrom}{sup -1}. In transverse scans spin wave peaks at E{sub q} = Dq{sup 2} appear as expected from early measurements performed with unpolarized neutrons. The longitudinal magnetic scattering {sub {chi}L}(q, E), on the other hand, is quasielastic without any signature of inelastic peaks near E{sub q}. The q and T dependences of {sub {chi}L}(q, E) resemble the paramagnetic scattering above {Tc}, i.e., the linewidth is roughly proportional to q{sup 2.5} and the integrated intensity I(q) is proportional to (q{sup 2} + {kappa}{sub z}{sup 2}){sup -1}. 8 refs., 3 figs.
Date:
October 10, 1989
Creator:
Boeni, P.; Martinez, J. L. & Tranquada, J. M.
Object Type:
Article
System:
The UNT Digital Library
Collins' bypass for the main ring
Design of the bypass for the main ring at Fermilab is discussed. Specific design features discussed include space, path length, geometric closure, matching of betatron functions, and external dispersion. Bypass parameters are given. (GHT)
Date:
August 10, 1982
Creator:
Ohnuma, S.
Object Type:
Report
System:
The UNT Digital Library
Examination of T-111 clad uranium nitride fuel pins irradiated up to 13,000 hours at a clad temperature of 990/sup 0/C
The examination of 27 fuel pins irradiated in the Plum Brook reactor facility is described. Curtailment of NASA sponsored nuclear programs prevented a complete examination of all pins. Nevertheless, results include fuel pin integrity, clad ductility, clad strain, fission gas release, fuel burnup, fuel swelling, neutron fluence, metallography, and instrumentation reliability. Twenty-two fuel pins were tested for fission gas leaks; 13 pins leaked with two having visible cracks. Fuel swelling appeared to be primarily burnup dependent for burnup values up to 2 at. %. Maximum burnup reached in these tests was 2.34 at. %. In general, the fuel pellets did not crack or crumble and fuel metallography remained unchanged. The amount of fission gas released from the fuel was low, generally less than 0.5%. The maximum amount released was 2%. No incompatibilities between fuel, liner, and clad were evident.
Date:
September 10, 1973
Creator:
Slaby, J.G.; Siegel, B.L.; Bowles, K.J. & Galbo, R.J.
Object Type:
Report
System:
The UNT Digital Library
Borehole cement and rock properties studies. Progress report for the period up to 1 August 1976
Research on the use of cements in radioactive waste isolation is reported. Other research is reported on the effects of thermal treatments of clays and shales on their cation exchange capacities and relative sorptive properties for cations. Development of instrumentation for measuring thermal properties of cements at atmospheric pressure was completed. A method was developed for measuring heat flow in shales and cement. Data on thermodynamic properties of cements and shales are included. Studies of shales, siltstones, and evaporites including scanning electron microscopy are in progress. (JRD)
Date:
August 10, 1976
Creator:
Roy, D. M.; Brindley, G. W.; McKinstry, H. A.; Voight, B.; Grutzeck, M.; Komarneni, S. et al.
Object Type:
Report
System:
The UNT Digital Library
Feasibility study: PASS computer environment
The Policy Analysis Screening System (PASS) is a computerized information-retrieval system designed to provide analysts in the Department of Energy, Assistant Secretary for Environment, Office of Technology Impacts (DOE-ASEV-OTI) with automated access to articles, computer simulation outputs, energy-environmental statistics, and graphics. Although it is essential that PASS respond quickly to user queries, problems at the computer facility where it was originally installed seriously slowed PASS's operations. Users attempting to access the computer by telephone repeatedly encountered busy signals and, once logged on, experienced unsatisfactory delays in response to commands. Many of the problems stemmed from the system's facility manager having brought another large user onto the system shortly after PASS was implemented, thereby significantly oversubscribing the facility. Although in March 1980 Energy Information Administration (EIA) transferred operations to its own computer facility, OTI has expressed concern that any improvement in computer access time and response time may not be sufficient or permanent. Consequently, a study was undertaken to assess the current status of the system, to identify alternative computer environments, and to evaluate the feasibility of each alternative in terms of its cost and its ability to alleviate current problems.
Date:
March 10, 1980
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Report exploring the differences and similarities in approach, and results of documents concerned with energy conservation in existing dwelling units. Final report
Literature on ways for saving energy by retrofitting single family homes was surveyed, and each energy conservation option is evaluated for economic desirability. The options considered include the prevention of heat losses by reducing air infiltration and by increasing thermal insulation, optimizing furnace operation, lowering space and water heater temperatures, flue gas heat recovery, and controlling hot water flow. The cost and payback period is given for each option. (LCL)
Date:
February 10, 1978
Creator:
Naismith, R.
Object Type:
Report
System:
The UNT Digital Library
Seal, dynamic inflatable, development test, installation and removal of
This specification establishes the requirements and procedures (using epoxy adhesive) for the installation and removal of the dynamic inflatable test seal for the Fast Flux Test Facility (FFTF), In-Vessel Handling Machine (IVHM) Reactor Refueling Plug (RRP).
Date:
June 10, 1974
Creator:
Deboi, H.H. & Ferrante, J.
Object Type:
Report
System:
The UNT Digital Library
Measurement control for plutonium isotopic measurements using gamma-ray spectrometry
A measurement control (MC) program should be an integral part of every nondestructive assay measurement system used for the assay of special nuclear materials. This report describes an MC program for plutonium isotopic composition measurements using high-resolution gamma-ray spectroscopy. This MC program emphasizes the standardization of data collection procedures along with the implementation of internal and external measurement control checks to provide the requisite measurement quality assurance. This report also describes the implementation of the MC program in the isotopic analysis code GRPAUT. Recommendations are given concerning the importance and frequency of the various MC checks in order to ensure a successful implementation of the MC procedures for the user's application.
Date:
May 10, 1985
Creator:
Fleissner, J.G.
Object Type:
Report
System:
The UNT Digital Library