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647
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461
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220
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133
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131
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100
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190
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113
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8,155 Matching Results
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Factors affecting visual inspection of thin film network
A study was made of various factors that affect the visual inspection of thin film networks. The effect of various types of reflected illumination, the effect of defect size or shape, the time required for inspection, and the inspection uniformity were evaluated. The use of polarized light is recommended for the visual inspection of thin film networks.
Date:
January 1, 1978
Creator:
Hines, R.E.
Object Type:
Report
System:
The UNT Digital Library
Development of ultrafiltration and inorganic adsorbents for reducing volumes of low-level and intermediate-level liquid waste: January--March 1978
The exposure of noncellulosic ultrafiltration membranes to a radioactive environment simulating up to 24 months of exposure to a beta dose of 10 ..mu..Ci/cm/sup 3/ and a gamma dose of 10/sup -5/ ..mu..Ci/cm/sup 3/ did not show any conclusive evidence of membrane degradation. Viscosity measurements for control membranes and irradiated membranes indicate no changes in polymer molecular weight were caused by the radiation exposure. This, in turn, suggests no physical or mechanical degradation took place. A continuous run on the ultrafiltration pilot plant was completed. The run lasted 33.5 hr; during this period, the flux declined from 4 gal/min to 0.8 gal/min while rejection of alpha activity increased slightly. A total of 20,000 gal were processed through the ultrafiltration system. The small laboratory column tests were continued with uranium-233 and americium-241. Several new resins were being evaluated along with the same type of resin as used before with uranium-233 and plutonium-238. Tests were continued with the 2-in. Engineering Columns using ultrafiltration product spiked with uranium-233.
Date:
April 27, 1978
Creator:
Koenst, J. W.; Herald, W. R. & Roberts, R. C.
Object Type:
Report
System:
The UNT Digital Library
ORIS: the Oak Ridge Imaging System program listings. [Nuclear medicine imaging with rectilinear scanner and gamma camera]
The Oak Ridge Imaging System (ORIS) is a general purpose access, storage, processing and display system for nuclear medicine imaging with rectilinear scanner and gamma camera. This volume contains listings of the PDP-8/E version of ORIS Version 2. The system is designed to run under the Digital Equipment Corporation's OS/8 monitor in 16K or more words of core. System and image file mass storage is on RK8E disk; longer-time image file storage is provided on DECtape. Another version of this program exists for use with the RF08 disk, and a more limited version is for DECtape only. This latter version is intended for non-medical imaging.
Date:
April 1, 1978
Creator:
Bell, P. R. & Dougherty, J. M.
Object Type:
Report
System:
The UNT Digital Library
Dielectric strengths of new gases and gas mixtures
It is emphasized that the most effective gaseous dielectrics are gas mixtures with components chosen on the basis of fundamental physicochemical knowledge, especially on low-energy electron-molecule interactions. On the basis of such lnowledge, especially on electron attachment and electron slowing down, a number of new gases and gas mixtures have been found with breakdown strengths superior to pure SF/sub 6/. These include the unitary gases c-C/sub 4/F/sub 8/ (perfluorocyclobutane), C/sub 4/F/sub 8/ (perfluorobutene-2), C/sub 4/F/sub 6/ (perfluoro-2-butyne), C/sub 6/F/sub 10/ (perfluorocyclohexene), C/sub 5/F/sub 8/ (perfluorocyclopentene), and C/sub 6/F/sub 12/ (perfluorodimethylcyclobutane), and the multicomponent gas mixtures 20% C/sub 4/F/sub 6/ + 80% SF/sub 6/, 40% C/sub 4/F/sub 6/ + 60% N/sub 2/, 50% C/sub 4/F/sub 6/ + 50% SF/sub 6/, and 30% C/sub 4/F/sub 6/ + 20% SF/sub 6/ + 50% N/sub 2/ with DC breakdown strengths relative to SF/sub 6/ of 1 equal to 1.4, 1.8, 2.2, 2.1, 2.2, 2,4, 1.3, 1.4, 1.75, and 1.33, respectively. Findings on these and other systems are presented and discussed. Also discussed are results on the dielectric strengths of some of the above new gases measured with cylindrical electrode geometries using different center conductor diameters. Finally, findings on the initial decomposition products of some …
Date:
January 1, 1978
Creator:
James, D.R.; Christophorou, L.G.; Pai, R.Y.; Pace, M.O.; Mathis, R.A.; Sauers, I. et al.
Object Type:
Article
System:
The UNT Digital Library
Thermal and electrical conductivities of high purity tantalum
The electrical resistivity and thermal conductivity of three high purity tantalum samples have been measured as functions of temperature over a temperature range of 5K to 65K. Sample purities ranged up to a resistivity ratio of 1714. The highest purity sample had a residual resistivity of .76 x 10/sup -10/OMEGA-m. The intrinsic resistivity varied as T/sup 3/./sup 9/ from 10K to 31K. The thermal conductivity of the purest sample had a maximum of 840 W/mK at 9.8K. The intrinsic thermal resistivity varied as T/sup 2/./sup 4/ from 10K to 35K. At low temperatures electrons were scattered primarily by impurities and by phonons with both interband and intraband transitions observed. The electrical and thermal resistivity is departed from Matthiessen's rule at low temperatures.
Date:
January 1, 1978
Creator:
Archer, S. L.
Object Type:
Report
System:
The UNT Digital Library
California solar data manual
Factors that determined the data contents of the manual are presented. Estimates of errors in the data are provided, and the impact of these errors on solar design is discussed. The state is divided into 15 solar zones of roughly similar solar radiation conditions, which are illustrated along with page references to the most relevant solar and climate data. A guide to the data tables and graphs is provided, which are displayed under solar, climate, and sky charts. A guide is given to simplified design methods to predict performance and cost of solar heating and cooling systems. (MHR)
Date:
January 1, 1978
Creator:
Berdahl, P.; Grether, D.; Martin, M. & Wahlig, M.
Object Type:
Report
System:
The UNT Digital Library
Western Gas Sands Project. Status report
The progress during December, 1977 of the major government sponsored endeavors undertaken to increase gas production from the low permeability gas sands of the western United States is summarized. The USGS is continuing geological and geophysical studies in the four major western basins to better characterize the resource base. Shipping arrangements for the core donated to the USGS by Inexco WASP (a well drilled for possible nuclear explosive stimulation in Wyoming) have been made, and cores for macrofossil and ostracode analysis from the Bowdoin Dome area have been collected. The National Laboratories, funded by DOE, are continuing their work in the area of research and development. The emphasis is on the development of new tools and instrumentation systems, rock mechanics, mathematical modeling and data analysis. Field tests and demonstrations active in the Uinta and Piceance Basins are Gas Producing Enterprises (GPE) Natural Buttes, Wells No. 14, 18, 19, 20, 21, and 22; Mobil Research and Development, Well No. F-31-13G; and Rio Blanco Natural Gas Company, Well No. 498-4-1. Colorado Interstate Gas Company has initiated activity on its project with the installation of equipment, and Mitchell Energy Company's proposal to conduct an MHF test in the Cotton Valley lime gas reservoir …
Date:
February 1, 1978
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Office of Waste Isolation progress report, January 1978
This document, prepared to report progress on the National Waste Terminal Storage (NWTS) program, consists of project reports on work performed by organizations under subcontract to OWI, by DOE contractors, by OWI consultants, and by other federal agencies participating in the NWTS program. The project reports are made under the headings technical projects, facility projects, planning and analysis, and regulatory affairs. (DLC)
Date:
February 28, 1978
Creator:
Zerby, C.D.
Object Type:
Report
System:
The UNT Digital Library
Cross sections for the /sup 7/Li(n,xn) and /sup 7/Li(n,n'. gamma. ) reactions between 1 and 20 MeV
Differential cross sections for the production of secondary neutrons and gamma rays from neutron interactions in /sup 7/Li have been measured at 50/sup 0/ and 126/sup 0/ (lab) for incident neutron energies in the range 1 to 20 MeV. An electron linac was used as a white neutron source. Incident neutron energies were determined using time-of-flight techniques for a source-to-sample distance of 48 m. Secondary spectra were determined by analysis of the pulse-height distributions observed in a NE-213 scintillation counter. The results are compared to the current evaluated data file (ENDF/B-IV, MAT 1272).
Date:
March 1, 1978
Creator:
Morgan, G. L.
Object Type:
Report
System:
The UNT Digital Library
Prediction of temperature increases in a salt repository expected from the storage of spent fuel or high-level waste
Comparisons in temperature increases incurred from hypothetical storage of 133 MW of 10-year-old spent fuel (SF) or high-level waste (HLW) in underground salt formations have been made using the HEATING5 computer code. The comparisons are based on far-field homogenized models that cover areas of 65 and 25 sq miles for SF and HLW, respectively, and near-field unit-cell models covering respective areas of 610 ft/sup 2/ and 400 ft/sup 2/. Preliminary comparisons based on heat loads of 150 kW/acre and 3.5 kW/canister indicated near-field temperature increases about 20% higher for the storage of the spent fuel than for the high-level waste. In these comparisons, it was also found that the thermal energy deposited in the salt after 500 years is about twice the energy deposited by the high-level waste. The thermal load in a repository containing 10-year-old spent fuel was thus limited to 60 kW/acre to obtain comparable far-field thermal effects as obtained in a repository containing 10-year-old high-level waste loaded at 150 kW/acre. Detailed far-field and unit-cell comparisons of transient temperature increases have been made based on these loadings. Unit-cell comparisons were made between a canister containing high-level waste with an initial heat production rate of 2.1 kW and a …
Date:
April 1, 1978
Creator:
Llewellyn, G.H.
Object Type:
Report
System:
The UNT Digital Library
Cold flow model test plan. Task IX. Technical support. Industrial low-Btu gas demonstration-plant program. (Deliverable No. 43)
A cold-flow model is being built to gather information for appropriately designing the venturi and the bottom section of the gasifier to attain the required ash discharge rate in the demonstration plant. Ancillary tasks will investigate the effect of different feed locations and different means of injecting fines. A model is necessary because the operating conditions of the pilot plant gasifier do not permit the type of testing required to meet the above objectives. The pilot plant gasifier has been operated with 2 and 3 in.-diameter venturis. Discharge rates through the venturi appropriate to the feed rates used have been on the order of 100 lb/hr. The demonstration plant design calls for a total ash agglomerate discharge from each gasifier of approximately 10,000 lb/hr. Scaling up venturi sizes and discharge rates from the pilot plant to the demonstration plant level is a primary motivation for building a cold-flow model. Larger sized venturis will be necessary to handle the larger discharge rates, and the model will be capable of incorporating up to an 8-in.-diameter venturi or other multiple-discharge nozzles. All equipment in the cold model will be capable of operation at 200 psig, which will enable testing to be conducted at …
Date:
June 1, 1978
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Health physics aspects of nuclear radiations from deuterium beam injectors
Estimations are made for X-ray generation from the accelerator column of various neutral beam injectors. For the case of deuterium beam operation where 2.5-MeV D-D neutrons pose a serious health physics concern, neutron and tritium production rates from beam targets are calculated for different beam energies. Biological doses from these radiations and shielding requirements are discussed.
Date:
February 1, 1978
Creator:
Kim, J.
Object Type:
Report
System:
The UNT Digital Library
Industrial Low Btu Fuel Gas Demonstration Plant Program: Phase I. Quarterly and annual report, 19 September 1977-31 December 1977
A major problem which arose during the reporting period was that of the completion of the required environmental analysis in order not to impact Phase II of the program. This problem was addressed and a proposed solution was agreed to. A sole source procurement justification for Energy Impact Associates was prepared and submitted to DOE for approval. This sole source procurement will enable construction start as scheduled (8 months after start of Phase II) whereas a competitive procurement of this item would have delayed that start by 6 months and with an additional inflationary cost to the program in excess of $5,000,000. The design work on the Commercial Plant is proceeding essentially on schedule. No major problems are foreseen. A major problem to be faced in 1978 is the achievement of successful operating data from the pilot plant necessary to confirm a demonstration plant design. This data must be obtained at a pressure of 3 atmospheres and requires additional modifications to the existing plant as described in IGT's Interface Plan submitted in January.
Date:
January 1, 1978
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
Quarterly Progress Report on Fission Product Behavior in LWRs for the Period October-December 1977
Analysis of release data obtained during High Burnup Fuel Test 10 (HBU-10) has been completed. In this test the fuel rod segment was ruptured by internal pressurization at 900/sup 0/C, at which time the temperature was rapidly increased to 1200/sup 0/C and maintained at this temperature for 10 min. Approximately 0.061% of the total cesium inventory in the rod segment was released; this was accompanied by the release of about 1.69% of the total /sup 85/Kr inventory. Moreover, about 0.022% of the fuel was ejected from the rod as particulates. The feasibility and conceptual design study for an experimental facility to verify fission product transport computational models has been completed. Although the study focused entirely on a facility which would be employed to verify those aspects of the transport models that dealt with fission product source-term attenuation factors in the primary coolant circuit external to the pressure vessel, the need for a second facility, to simulate conditions within the pressure vessel, was also indicated.
Date:
February 1, 1978
Creator:
Malinauskas, A. P.; Lorenz, R. A.; Collins, J. L.; Osborne, M. F.; Whatley, S. K. & Towns, R. L.
Object Type:
Report
System:
The UNT Digital Library
Development of ultrafiltration and inorganic adsorbents for reducing volumes of low-level and intermediate-level liquid waste: October--December 1977
The exposures of noncellulosic ultrafiltration membranes to a radioactive environment simulating up to 24 months of exposure to a ..beta.. dose of 10 ..mu..Ci/cm/sup 3/, a ..gamma.. dose of 10/sup -5/ ..mu..Ci/cm/sup 3/, and an ..cap alpha.. dose of 4.9 x 10/sup -3/ ..mu..Ci/cm/sup 3/ were completed. Exposure to ..beta.. and ..gamma.. radiation did not affect membrane performance. After a simulated six months of exposure to ..cap alpha.. radiation some degradation of membrane performance occurred. Several experiments were made on a laboratory-scale reverse-osmosis unit using the product from ultrafiltration as feed. Rejection of activity ranged from 88 to 99 percent. The ''continuous'' ultrafiltration pilot run was completed. Approximately 40,000 gal were processed in over 70 hr of operating time without shutdown for cleaning. Flux and rejection were maintained relatively steady over this period. Rejection of gross alpha ranged from 80 to 99.5 percent depending on the ionic content of the waste stream. Flux rates ranged from 5 to 8 liters/min over this period. The engineering column tests were continued using uranium-233 with product from the ultrafiltration pilot plant. Flow rates and pH were varied in order to determine optimum operating conditions.
Date:
February 24, 1978
Creator:
Koenst, J. W.; Herald, W. R. & Roberts, R. C.
Object Type:
Report
System:
The UNT Digital Library
Liquid waste handling facilities for a conceptual LWR spent fuel reprocessing complex
The waste evaporator systems and the methods for evaporating the liquid wastes of various radioactivity levels are discussed. After the liquid wastes are evaporated and nitric acid is recovered the high-level liquid waste is incorporated into borosilicate glass and the intermediate-level liquid waste into concrete for final disposal. (LK)
Date:
January 1, 1978
Creator:
Witt, D.C. & Bradley, R.F.
Object Type:
Article
System:
The UNT Digital Library
Penn Grade Micellar Displacement project. First annual report, June 1975--June 1976
The main objective of the Penn Grade-ERDA Micellar Displacement Project is to assess and hopefully, demonstrate the feasibility of commercial application of the micellar-polymer process for tertiary oil recovery from a rather large, but relatively ''tight'' section of the Bradford Third Sand. The initial phase of this project involves pertinent core and field injectivity measurements from a freshly drilled well, as a basis for assessing the feasibility of a small demonstration test flood to be performed under Phase II. This report details the work done and results obtained under Phase I (Injectivity Test) completed during the first year of the project. These results, having indicated that the pattern test envisaged under Phase II is indeed feasible, work is now in progress to carry the project to the pattern test phase, in pursuit of project goals.
Date:
March 1, 1978
Creator:
Danielson, H. H.; Paynter, W. T.; Midkiff, F. R. & Finalle, L. L.
Object Type:
Report
System:
The UNT Digital Library
Equipment develoment report: downhole fluid injector
The development, design, fabrication, and operation of a tool used for injecting a discrete quantity of fluid (e.g. a dye) at a desired location within a hot geothermal borehole are described. Assembly and operating instructions are included.
Date:
February 1, 1978
Creator:
Archuleta, J. R.; Fink, C. F. & Kurtenbach, J.
Object Type:
Report
System:
The UNT Digital Library
Fabrication of a 180/sup 0/ electron scattering facility. Final report, January 2, 1975--January 1, 1978
A system of four dipole magnets to be used for 180/sup 0/ electron scattering studies at the 400 MeV William F. Bates Electron Linear Accelerator of Middleton, Massachusetts was constructed and tested. The first three magnets through which the incident beam passes have similar pole shapes and serve only as beam transport elements. The fourth magnet directs the incident beam onto a target, and also receives and deflects the backscattered electrons into a large magnetic spectrometer operating in an energy-loss mode. The system may be used for both elastic and inelastic electron scattering without moving the spectrometer. The incident beam and the post-target beam travel along the same line. Tests show that a constant solid angle is maintained for scattering regardless of the energy loss suffered by the electron in the target. A resolution inherent to the system of less than 2.5 x 10/sup -4/ was found.
Date:
January 1, 1978
Creator:
Peterson, G A
Object Type:
Report
System:
The UNT Digital Library
Impact of increased coal consumption in the Pacific Northwest
The objectives of the National Coal Utilization Assessment are: Identification of the environmental, health and socioeconomic impacts to be expected from the increased use of coal; investigation of mitigation strategies that might be used to manage these impacts; and establishment of working relationships with state and regional agencies and utilities. A number of energy issues were identified in the course of the study. Probably the most significant issues in this region are the siting of coal-fired power plants and the tradeoff in water allocation between energy and agriculture. Choices of coal-fired generation sites and water use determine the level of impacts to air, water, land, terrestrial and aquatic ecosystems, and human health and socioeconomics. Air quality impacts were studied by incorporating current and projected emission inventories into both short-range and long-range air quality diffusion models. Results indicate that annual average ambient air quality standards will not be exceeded at any of the sites. Surface water supplies are more than adequate to meet the needs of new coal-fired generating plants located in the Columbia or Snake River; however, future conflicts could arise with agriculture over allocation of water rights. Water quality impacts would be minimal, even in the delicate estuarine and …
Date:
March 1, 1978
Creator:
Burnham, J.B. (comp.)
Object Type:
Report
System:
The UNT Digital Library
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
CHILES 2: a finite element computer program that calculates the intensities of linear elastic singularities in isotropic and orthotropic materials
CHILES 2 is a finite-element computer program that calculates the strength of singularities in linear elastic bodies. A generalized quadrilateral finite element that includes a singular point at a corner node is incorporated in the code. The displacement formulation is used and interelement compatibility is maintained so that monotone convergence is preserved. Plane stress, plane strain, and axisymmetric conditions are treated. Isotropic and orthotropic crack tip singularity problems are solved by this version of the code, but any type of singularity may be properly modeled by modifying selected subroutines in the program.
Date:
February 1, 1978
Creator:
Benzley, S.E. & Beisinger, Z.E.
Object Type:
Report
System:
The UNT Digital Library
Stability of plutonium contaminated sediments in the Miami--Erie Canal. [Mound Facility, Ohio, radioactive effluents monitoring]
This study was conducted to evaluate the stability of plutonium-contaminated sediment in the Miami-Erie Canal. Correlations were sought to relate concentrations at air sampling stations to plutonium-238 concentrations in air and stack emissions, wind direction, particulate loading, rainfall, and construction activities. There appears to be some impact on airborne concentrations at air sampling stations 122 and 123 from the contaminated sediment in the canal and ponds area. For purposes of this evaluation, it was assumed that the plutonium-238 found in the air samples came from the contaminated sediment in the canal/ponds area. To complete the evaluation of the inhalation pathway, dose calculations were performed using actual airborne concentrations of plutonium-238 measured at sampler 123. The dose equivalent to an individual in that area was calculated for 1 yr and 70 yr. Dose calculations were also performed on potential uptake of contaminated vegetation from that area for 1 yr and 70 yr. This study indicates that, although the contaminated sediments in the canal and pond area appear to contribute to airborne plutonium-238, the observed maximum monthly concentration of plutonium-238 in air is a small fraction of the DOE Radioactivity Concentration Guide (RCG) and the nine-month average concentration of plutonium-238 in air …
Date:
March 1, 1978
Creator:
Farmer, Billy M. & Carfagno, Daniel G.
Object Type:
Report
System:
The UNT Digital Library
Fiber optics and microprocessors: a control-system solution for the laser-fusion environment
The use of fiber optics and microprocessors in a distributed computer control system for a 100-kJ CO/sub 2/ laser fusion facility is described. Gas-laser control systems must operate in an environment in which megavolt Marx circuits generate megampere discharges in the laser amplifiers, with attendant high electromagnetic fields. By linking the distributed controls with fiber optics the adverse effect of these fields on the hard-wired controls is mimimized, and the additional advantage of ground isolation gained. Fiber-optic subsystems and interfaces include low-error-rate digital communication links between computers; nanosecond timing and trigger links; fiber-optic parameter monitors with dc-to-10 MHz bandwidths; binary fiber-optic power control for valves, motors, and contactors; and binary fiber-optic status interfaces to monitor the system response to control outputs.
Date:
January 1, 1978
Creator:
Thuot, M.E.
Object Type:
Article
System:
The UNT Digital Library