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Ceramic technology for Advanced Heat Engines Project
Significant accomplishments in fabricating ceramic components for advanced heat engine programs have provided evidence that the operation of ceramic parts in high-temperature engine environments is feasible. However, these programs have also demonstrated that additional research is needed in materials and processing development, design methodology, and database and life prediction before industry will have a sufficient technology base from which to produce reliable cost-effective ceramic engine components commercially. An assessment of needs was completed, and a five year project plan was developed with extensive input from private industry. The project approach includes determining the mechanisms controlling reliability, improving processes for fabricating existing ceramics, developing new materials with increased reliability, and testing these materials in simulated engine environments to confirm reliability. Although this is a generic materials project, the focus is on the structural ceramics for advanced gas turbine and diesel engines, ceramic bearings and attachments, and ceramic coatings for thermal barrier and wear applications in these engines. To facilitate the rapid transfer of this technology to US industry, the major portion of the work is being done in the ceramic industry, with technological support from government laboratories, other industrial laboratories, and universities. This project is managed by ORNL for the Office …
Date:
July 1, 1991
Creator:
Johnson, D. R.
System:
The UNT Digital Library
Delineation of an electrical resistivity anomaly, Malpais area, Beowawe KGRA, Eureka and Lander Counties, Nevada
A simple numerical model of previously released bipole-dipole resistivity data shows the margin of the graben to be anomalously conductive below the Malpais. The conductive area has been delineated with data from a dipole-dipole resistivity survey run in April 1980 for this study. Detailed numerical models of these data define a 1250 m wide body with resistivities less than 20 ohm-m that appear to connect The Geysers and the graben boundary. The minimum depth to the conductor is interpreted to be 375 m; its depth extent is undetermined. The electrical data do not resolve whether the anomaly below the Malpais may be the product of a defunct hydrothermal system or the signature of an active system. If thermal gradient data detect an enhanced heat flow anomaly in the same area, the Malpais may be a viable geothermal exploration target within the Beowawe KGRA.
Date:
July 1, 1980
Creator:
Smith, C.
System:
The UNT Digital Library
Treatment of dynamical processes in two-dimensional models of the troposphere and stratosphere
The physical structure of the troposphere and stratosphere is the result of an intricate interplay among a large number of radiative, chemical, and dynamical processes. Because it is not possible to model the global environment in the laboratory, theoretical models must be relied on, subject to observational verification, to simulate atmospheric processes. Of particular concern in recent years has been the modeling of those processes affecting the structure of ozone and other trace species in the stratosphere and troposphere. Zonally averaged two-dimensional models with spatial resolution in the vertical and meridional directions can provide a much more realistic representation of tracer transport than one-dimensional models, yet are capable of the detailed representation of chemical and radiative processes contained in the one-dimensional models. The purpose of this study is to describe and analyze existing approaches to representing global atmospheric transport processes in two-dimensional models and to discuss possible alternatives to these approaches. A general description of the processes controlling the transport of trace constituents in the troposphere and stratosphere is given.
Date:
July 1, 1980
Creator:
Wuebbles, D.J.
System:
The UNT Digital Library
Technical-economic assessment of the production of methanol from biomass. Executive summary. Final research report
The results are presented of a comprehensive systems study which assessed the engineering and economic feasibilities of the production of methanol from biomass utilizing existing technology. The three major components of the biomass to methanol system assessed are the availability of biomass feedstocks, the thermochemical conversion of biomass to methanol fuels, and the distribution and markets for methanol fuels. The results of this study show that methanol fuel can be produced from biomass using commercially available technology in the near term, and could be produced economically in significant quantities in the mid-to-late 1980's when advanced technology is available.
Date:
July 12, 1979
Creator:
Wan, E. I.; Simmons, J. A.; Price, J. D. & Nguyen, T. D.
System:
The UNT Digital Library
SPERT IV HAZARDS SUMMARY REPORT
Spert IV is a large pool-type experimental facility for reactor kinetic studies. These studies will include power excursion and instability tests for a variety of reactor designs. Since the Spert IV experimental program requires the performance of tests which will approach, and may exceed the threshold of reactor destruction, the probability of occurrence of the maximum possible accident is not negligible compared with that of other possible accidents. The maximum possible accident for this facility is considered to be a severe nuclear excursion which results in the destruction of the reactor building and the release of 100% of the accumulated fission product inventory of the atmosphere in a steam cloud. The fission product source assumed in the analysis of this accident is an upper limit in view of the nature of the tests to be performed and the heat removal capacity of the system. This postulated accident is independent of the details of core and control system design and is valid for all cores anticipated for use in the experimental program. The major hazards present in the operation of this facility, the precautions to be taken to reduce the probability of an accident, and the consequences of the maximum possible …
Date:
July 1, 1961
Creator:
Bentzen, F. L. & Crocker, J. G.
System:
The UNT Digital Library
OXIDATION OF GRAPHITE UNDER HIGH TEMPERATURE REACTOR CONDITIONS
A kinetic study was conducted to provide information on oxidation of reactor graphites in the temperature range of 450 to 675 deg C and on the effects of reactor environment on oxidation rates. Among the parameters studied were chemical reactivity of the graphite, prior oxidation, a high intensity gamma flux during oxidation, variation of the surface-to-volume ratio of the graphite specimens, neutron bombardment prior to oxidation exposure, and gas flow rates. Rate equations showed apparent activation energies of 50 kcal/mole in the absence of radiation and 30 kcal/mole in the presence of a 1 x 10/sup 6/ r/hr gamma flux. (auth)
Date:
July 1, 1961
Creator:
Dahl, R.E.
System:
The UNT Digital Library
EXPERIMENTAL MEASUREMENTS OF THE SUCTION HEAD REQUIRED BY THE HALLAM PROTOTYPE FREE SURFACE SODIUM PUMP
Hydraulic tests were made on the Hallam Prototype Free-Surface Sodium Pump to determine the net positive suction head (NPSH) required at various sodium flow rates. Pump performance data were also collected. The results indicate that an NPSH of 22 ft sodium is required at the design flow rate of 7200 gpm at approximates 1000 deg F, agreeing with computed values, and that the pump is designed with a safety margin of slightly over l0%. (D.L.C.)
Date:
July 25, 1961
Creator:
Atz, R.W.
System:
The UNT Digital Library
Filter characterization. [ANLYZ computer code]
Some insight into the characteristic response of filters versus frequency and loading is presented. A computer program is provided which will allow the user to vary the filter model in order to assess the effect of specific conditions.
Date:
July 1, 1982
Creator:
Stanton, C.P.
System:
The UNT Digital Library
PNL technical review of pressurized thermal-shock issues. [PWR]
Pacific Northwest Laboratory (PNL) was asked to develop and recommend a regulatory position that the Nuclear Regulatory Commission (NRC) should adopt regarding the ability of reactor pressure vessels to withstand the effects of pressurized thermal shock (PTS). Licensees of eight pressurized water reactors provided NRC with estimates of remaining effective full power years before corrective actions would be required to prevent an unsafe operating condition. PNL reviewed these responses and the results of supporting research and concluded that none of the eight reactors would undergo vessel failure from a PTS event before several more years of operation. Operator actions, however, were often required to terminate a PTS event before it deteriorated to the point where failure could occur. Therefore, the near-term (less than one year) recommendation is to upgrade, on a site-specific basis, operational procedures, training, and control room instrumentation. Also, uniform criteria should be developed by NRC for use during future licensee analyses. Finally, it was recommended that NRC upgrade nondestructive inspection techniques used during vessel examinations and become more involved in the evaluation of annealing requirements.
Date:
July 1, 1982
Creator:
Pedersen, L. T.; Apley, W. J.; Bian, S. H.; Defferding, L. J.; Morgenstern, M. H.; Pelto, P. J. et al.
System:
The UNT Digital Library
Electron energy loss spectroscopy of CH/sub 3/N/sub 2/CH/sub 3/ adsorbed on Ni(100), Ni(111), Cr(100), Cr(111)
A study of the adsorption of CH/sub 3/N/sub 2/CH/sub 3/ on Ni(100), Ni(111), Cr(100), and Cr(111) using high resolution electron energy loss spectroscopy (EELS) is presented. Under approximately the same conditions of coverage, the vibrational spectra of CH/sub 3/N/sub 2/CH/sub 3/ on these four surfaces are quite distinct from one another, implying that the CH/sub 3/N/sub 2/CH/sub 3/-substrate interaction is very sensitive to the physical and electronic structure of each surface. In addition to the room temperature studies, the evolution of surface species on the Ni(100) surface in the temperature range 300 to 425 K was studied. Analysis of the Ni(100) spectra indicates that molecular adsorption, probably through the N lone pair, occurs at room temperature. Spectra taken after annealing the CH/sub 3/N/sub 2/CH/sub 3/-Ni(100) surfaces indicate that CH and CN bond scission occurred at the elevated temperatures. Decomposition of CH/sub 3/N/sub 2/CH/sub 3/ takes place on the Ni(111), Cr(100), and Cr(111) surfaces at room temperature, as evidenced by the intensity of the carbon-metal stretch in the corresponding spectra. Possible identities of coadsorbed dissociation products are considered. The stable coverage of surface species on all four surfaces at 300 K is less than one monolayer. A general description of an …
Date:
July 1, 1985
Creator:
Schulz, M.A.
System:
The UNT Digital Library
Study of roughness-induced diffuse and specular reflectance at silver-air and silver-liquid interfaces. Final report, July 1, 1979-August 31, 1980
Results of an extended investigation of surface plasma-wave absorption and roughness-induced optical scattering from an interface of silver and air are described. In particular, the position of the surface plasma resonance minimum in reflectivity for a stochastically roughened metal silver surface has been studied as a function of a number of distinct roughness perturbations. In the case of a transparent liquid-silver boundary the frequency red shift of the resonance minimum has been determined and the location of the surface plasmon dip for various liquids is shown to agree well with a simple roughness theory. The additional interfacial properties due to the formation of a thin inhomogeneous oxide layer occurring either spontaneously or due to application of a small interfacial electrical potential are more complex. However, the optical constants of the interlayer have been determined from differential specular reflectance measurements at the boundary. Nodule size parameters determined from scattering and absorption measurements and features of both polarized and depolarized diffuse reflectance give further information on the state of the interface. Reflectance of ordered-corrugated surfaces are also described.
Date:
July 1, 1980
Creator:
Sari, S.O.
System:
The UNT Digital Library
HIFI: a computer code for projectile fragmentation accompanied by incomplete fusion
A brief summary of a model proposed to describe projectile fragmentation accompanied by incomplete fusion and the instructions for the use of the computer code HIFI are given. The code HIFI calculates single inclusive spectra, coincident spectra and excitation functions resulting from particle-induced reactions. It is a multipurpose program which can calculate any type of coincident spectra as long as the reaction is assumed to take place in two steps.
Date:
July 1, 1980
Creator:
Wu, J.R.
System:
The UNT Digital Library
Transport of solid commodities via freight pipeline: demand analysis methodology. Volume IV. First year final report
In order to determine the feasibility of intercity freight pipelines, it was necessary to determine whether sufficient traffic flows currently exist between various origins and destinations to justify consideration of a mode whose operating characteristics became competitive under conditions of high-traffic volume. An intercity origin/destination freight-flow matrix was developed for a large range of commodities from published sources. A high-freight traffic-density corridor between Chicago and New York and another between St. Louis and New York were studied. These corridors, which represented 18 cities, had single-direction flows of 16 million tons/year. If trans-shipment were allowed at each of the 18 cities, flows of up to 38 million tons/year were found in each direction. These figures did not include mineral or agricultural products. After determining that such pipeline-eligible freight-traffic volumes existed, the next step was to determine the ability of freight pipeline to penetrate such markets. Modal-split models were run on aggregate data from the 1967 Census of Transportation. Modal-split models were also run on disaggregate data specially collected for this study. The freight pipeline service characteristics were then substituted into both the aggregate and disaggregate models (truck vs. pipeline and then rail vs. pipeline) and estimates of pipeline penetration into particular …
Date:
July 1, 1976
Creator:
Allen, W.B. & Plaut, T.
System:
The UNT Digital Library
Proceedings of the 1960 Idaho Conference on Reactor Kinetics Held at Sun Valley, Idaho, October 12-14, 1960
>Thirty papers are included on reactor kinetics with emphasis being placed on reactor safety and design considerations resulting from kinetic work. Information is presented on power excursion programs, reactor transfer function determination and application, reactor instability and thermal-hydraulic problems, and analytical methods in reactor kinetics. The accomplishments in the field and areas needing emphasis are discussed and summarized. Constructive suggestions are made on program direction and information dissemination. Separate abstracts were prepared for each paper. (N.W.R.) lOl2 Data and analytical work on various power excursion tests are summarized and discussed in order to show the present position and understanding of reactor kinetics under accident conditions. The results show that our understanding of plate-type, water-moderated systems of the low power research type seem to be in good shape. On the other hand, information on radiolytic gas formation and transient boiling phenomena is not understood too well. Data are primarily presented on safety experiments with SPERT I and KEWB; however, some information is presented on power excursion tests of Borax I, SPERT III, Triga, Treat, and Godiva. Results show that the problem of predicting the response of reactor systems is on a much firmer basis, even without knowing very much about details. …
Date:
July 1, 1962
Creator:
Haire, J. C. & Bright, G. O.
System:
The UNT Digital Library
Preliminary report on the promise of accelerator-driven natural-uranium-fueled light-water-moderated breeding power reactors
A new concept for a power breeder reactor that consists of an accelerator-driven subcritical thermal fission system is proposed. In this system an accelerator provides a high-energy proton beam which interacts with a heavy-element target to produce, via spallation reactions, an intense source of neutrons. This source then drives a natural-uranium-fueled, light-water-moderated and -cooled subcritical blanket which both breeds new fuel and generates heat that can be converted to electrical power. The report given presents a general layout of the resulting Accelerator Driven Light Water Reactor (ADLWR), evaluates its performance, discusses its fuel cycle characteristics, and identifies the potential contributions to the nuclear energy economy this type of power reactor might make. A light-water thermal fission system is found to provide an attractive feature when designed to be source-driven. The equilibrium fissile fuel content that gives the highest energy multiplication is approximately equal to the content of /sup 235/U in natural uranium. Consequently, natural-uranium-fueled ADLWRs that are designed to have the highest energy generation per source neutron are also fuel-self-sufficient; that is, their fissile fuel content remains constant with burnup. This feature allows the development of a nuclear energy system that is based on the most highly developed fission technology …
Date:
July 1, 1977
Creator:
Greenspan, E.
System:
The UNT Digital Library
Use Test Comparison of TBP Diluents
Several diluents for possible use in TBP Purex Plant solvent were tested. The tests included nitric --nitrous acid degradation, fission prcduct distribution under simulated plant conditions, emulsillcation, and radiolysis. The order of quality of four diluents is n-dcdecane> Soltrol 170> Shell Code 85030(82000)> Shell E-2342. (D.L.C.)
Date:
July 1, 1961
Creator:
Mendel, J. E.
System:
The UNT Digital Library
Energy and technology review
The state of the laboratory address by LLNL Director Roger Batzel is summarized, and a breakdown of the laboratory funding is given. The Livermore defense-related committment is described, including the design and development of advanced nuclear weapons as well as research in inertial confinement fusion, nonnuclear ordnance, and particle beam technology. LLNL is also applying its scientific and engineering resources to the dual challenge of meeting future energy needs without degrading the quality of the biosphere. Some representative examples are given of the supporting groups vital for providing the specialized expertise and new technologies required by the laboratory's major research programs. (GHT)
Date:
July 1, 1982
Creator:
Stowers, I.F.; Crawford, R.B.; Esser, M.A.; Lien, P.L.; O'Neal, E. & Van Dyke, P. (eds.)
System:
The UNT Digital Library
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
System:
The UNT Digital Library
Exact calculations of nuclear-recoil energies from prompt gamma decays resulting from neutron capture
The results of an accurate determination of the recoil spectrum from (n, ..gamma..) reactions in molybdenum are presented. The recoil spectrum has been calculated from nuclear level structure data and measured branching ratios. Angular correlations between successive gammas have been accounted for using the standard theoretical techniques of Racah algebra and the density matrix formalism.
Date:
July 20, 1981
Creator:
Kinney, J.H.
System:
The UNT Digital Library
Comparative ranking of 0. 1-10 MW/sub e/ solar thermal electric power systems. Volume II. Supporting data. Final report
This report is part of a two-volume set summarizing the results of a comparative ranking of generic solar thermal concepts designed specifically for electric power generation. The original objective of the study was to project the mid-1990 cost and performance of selected generic solar thermal electric power systems for utility applications and to rank these systems by criteria that reflect their future commercial acceptance. This study considered plants with rated capacities of 1-10 MW/sub e/, operating over a range of capacity factors from the no-storage case to 0.7 and above. Later, the study was extended to include systems with capacities from 0.1 to 1 MW/sub e/, a range that is attractive to industrial and other nonutility applications. Volume I summarizes the results for the full range of capacities from 0.1 to 1.0 MW/sub e/. Volume II presents data on the performance and cost and ranking methodology.
Date:
July 1, 1980
Creator:
Thornton, J.P.; Brown, K.C.; Finegold, J.G.; Gresham, J.B.; Herlevich, F.A. & Kriz, T.A.
System:
The UNT Digital Library
Detailed Stress Analysis of SM-1 Steam Generator Tube Sheet
The detailed stress analysis of the SM-1 steam generator tube sheet showed it to be safe from strain cycling damage. However, the pressure stresses were greater than the yield strength during the hydrostatic test. The differential between pressure stresses and yield strength indicates that some initial deformation may have taken place in the tube sheet. (auth)
Date:
July 11, 1962
Creator:
Busuttil, J. J. & Chittum, R. A.
System:
The UNT Digital Library
Input and decayed values of radioactive liquid wastes discharged to the ground in the 200 Areas through 1975
Low and intermediate level liquid wastes from chemical separations processing of spent reactor fuel elements have been discharged to the ground in the 200-Areas since 1944. Large volumes of process cooling water, normally free of radioactive contaminants, are discharged to surface ditches or natural surface depressions (ponds). Lesser volumes of liquid waste such as steam condensates, process condensates, scavenged process waste supernatants, and plutonium processing wastes have been, or are being discharged to subsurface disposal sites (cribs). Only input volumes and radioactivity discharged to each disposal site have been reported periodically.
Date:
July 8, 1976
Creator:
Anderson, J. D.
System:
The UNT Digital Library
Wells 1/sup 0/ x 2/sup 0/ NTMS area, Nevada. Data report (abbreviated)
Surface sediment samples were collected at 1336 sites, at a target sampling density of one site per 13 square kilometers. Ground water samples were collected at 112 sites. Neutron activation analysis results are given for uranium and 16 other elements in sediments, and for uranium and 9 other elements in ground water and surface water. Mass spectrometry results are given for helium in ground water. Field measurements and observations are reported for each site. Data from ground water and surface water sites include (1) water chemistry measurements (pH, conductivity, and alkalinity), (2) physical measurements where applicable (water temperature, well description, and scintillometer reading), and (3) elemental analyses (U, Al, Br, Cl, Dy, F, Mg, Mn, Na, and V). Helium analyses are given for ground water. Data from sediment sites include (1) stream water chemistry measurements from sites where water was available, and (2) elemental analyses for sediment samples (U, Th, Hf, Al, Ce, Dy, Eu, Fe, La, Lu, Mn, Sc, Sm, Na, Ti, V, and Yb). Areal distribution maps, histograms, and cumulative frequency plots for most elements; U/Th, U/Hf, U/(Th + Hf), and U/La ratios; and scintillometer readings at sediment sample sites are included.
Date:
July 1, 1980
Creator:
Cook, J. R.
System:
The UNT Digital Library
Mechanical Engineering Department technical abstracts
The Mechanical Engineering Department publishes listings of technical abstracts twice a year to inform readers of the broad range of technical activities in the Department, and to promote an exchange of ideas. Details of the work covered by an abstract may be obtained by contacting the author(s). Overall information about current activities of each of the Department's seven divisions precedes the technical abstracts.
Date:
July 1, 1982
Creator:
Denney, R.M. (ed.)
System:
The UNT Digital Library