7,158 Matching Results

Results open in a new window/tab.

Sintering of polycrystalline ionic conductors:. beta. ''-Al/sub 2/O/sub 3/ and NASICON (open access)

Sintering of polycrystalline ionic conductors:. beta. ''-Al/sub 2/O/sub 3/ and NASICON

The densification kinetics for both ..beta..''-alumina and NASICON are dramatically different. ..beta..''-Alumina sinters by a reactive liquid process whereas NASICON densifies by a solid state method. More importantly, a qualitative examination of particle and agglomerate distributions, phase composition, linear shrinkage analysis, and heating rate effects can result in a concise determination of sintering processes without recourse to more quantitative techniques. Such a simple procedural method should be a basis for any beginning investigative study into the densification mechanism of new multicomponent ceramic materials.
Date: January 1, 1979
Creator: McEntire, B. J.; Miller, G. R. & Gordon, R. S.
Object Type: Article
System: The UNT Digital Library
Redox reactions involving chromium, plutonium, and manganese in soils (open access)

Redox reactions involving chromium, plutonium, and manganese in soils

Plutonium speciation in soils is discussed. Chromium was selected as a model for studying soil Pu. Similarities between Cr and Pu are pointed out, and a hypotheses concerning Pu speciation in soils is presented. Findings from Cr oxidation studies that may be relevant to the problem of Pu oxidation in soils are discussed. (JGB)
Date: January 1, 1979
Creator: Amacher, M.C. & Baker, D.E.
Object Type: Report
System: The UNT Digital Library
Intermediate-depth geothermal temperature study. Gradient holes: 11-33 and 63-33, Soda Lake, NV (open access)

Intermediate-depth geothermal temperature study. Gradient holes: 11-33 and 63-33, Soda Lake, NV

During 1979, Chevron Resources Company drilled two 2000 ft holes near Soda Lake in the Nevada Carson Sink area to obtain subsurface data for inclusion in the US Department of Energy's Northern Basin and Range geothermal reservoir assessment program. Drilling information together with detailed lithologic, geophysical and temperature log data were compiled for each hole and is summarized in this report. Maximum stabilized temperatures of 297/sup 0/F and 367/sup 0/F were encountered at total depth in each of the holes, respectively.
Date: October 1, 1979
Creator: Hill, D.G.
Object Type: Report
System: The UNT Digital Library
Phosphate-bonded glass cements for geothermal wells. Final report (open access)

Phosphate-bonded glass cements for geothermal wells. Final report

Calcium aluminosilicate glasses were found to react with phosphoric acid in three ways depending upon silica content. Above 55% SiO/sub 2/ they are insoluble while below 50% they dissolve readily. The transition compositions release calcium and aluminum ions and a silica gel phase replaces the glass. Activation energies in the order of 10 kcal/mole are associated with the dissolution. Equilibrium studies in the systems CaO-P/sub 2/O/sub 5/-H/sub 2/O, Al/sub 2/O/sub 3/-P/sub 2/O/sub 5/-H/sub 2/O, and CaO-Al/sub 2/O/sub 3/-P/sub 2/O/sub 5/-H/sub 2/O were made to determine the phases which are stable at 200/sup 0/C in excess water. The CaO system shows hydroxylapatite, monetite and monocalcium orthophosphate are the stable phases. The Al/sub 2/O/sub 3/ system contains augelite, berlinite, and a high phosphate aluminum hydrate. The quaternary system shows the above phase plus a lime alumina hydrogarnet and crandallite. Cement made from a glass frit of the composition 45% SiO/sub 2/: 24% CaO: 24% Al/sub 2/O/sub 3/ has a compressive strength of 500 psi after several days in steam at 200/sup 0/C and 800 psi after months in steam. Bonding of cements to mild steel are discussed.
Date: September 1, 1979
Creator: Rockett, T.J.
Object Type: Report
System: The UNT Digital Library
Fusion utilization projections in the United States energy economy (open access)

Fusion utilization projections in the United States energy economy

The following topics are discussed in some detail in this report: (1) applications of fusion energy, (2) fusion implementation in the US energy system, (3) reactor performance requirements, (4) technology for electric applications, and (5) technology for synthetic fuel/chemical applications. (MOW)
Date: November 1, 1979
Creator: Powell, J.R. & Fillo, J.A.
Object Type: Report
System: The UNT Digital Library
Review of recent measurements of charmed particle lifetimes using emulsions (open access)

Review of recent measurements of charmed particle lifetimes using emulsions

This talk is a review of results which have been reported during the past year on charmed particle decays in emulsions.
Date: December 1, 1979
Creator: Voyvodic, L.
Object Type: Article
System: The UNT Digital Library
Field radiography using 100 Ci of Co-60 without interrupting adjacent manufacturing operations (open access)

Field radiography using 100 Ci of Co-60 without interrupting adjacent manufacturing operations

Radiography is the primary method of Nondestructive Examination recognized by the ASME B and PV Code as providing objective evidence of volumetric examination of the pressure boundary welds that are present in the Clinch River Breeder Reactor Program (CRBRP) Steam Generator. In order to support the steam generator production schedule, the radiographic examinations must be performed without interrupting any other manufacturing or inspection operations taking place within a 20-ft radius from the source. This condition imposes rigorous radiation safety requirements since the gamma radiation sources chosen to be used for examination of the pressure boundary welds, Co-60 and Ir-192, are very energetic. Co-60 gamma ray energy is 1.17 and 1.33 MeV and Ir-192 gamma ray is .6 MeV. The hazard of using such a high energy sources in the immediate vicinity of working personnel has necessitated the need for a thorough evaluation of methods of protection. Personnel protection from penetrating radiation, both x-ray and gamma ray, is accomplished by ingenious use, singly or in combination, of two factors which reduce radiation intensity. These factors are distance and shielding. In all radiographic operations the primary consideration is for personnel safety. The maximum radiation dose rate limit will be 0.002 rem/hr. This …
Date: January 1, 1979
Creator: Donnelly, C.W.
Object Type: Article
System: The UNT Digital Library
Staff rosters for 1979: environmental programs (open access)

Staff rosters for 1979: environmental programs

The roster of the scientific and professional staffs of the Environmental Programs of the Department of Energy and Environment has been compiled as of December 1979. Staff members have been listed according to their organizational units, i.e., the Atmospheric Sciences Division, the Environmental Chemistry Division, the Oceanographic Sciences Division, and the Land and Freshwater Environmental Sciences Group. Educational background, research interests, professional activities, summary of experience at BNL, and selected publications have been included for each member listed.
Date: December 1, 1979
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Decommissioning of commercial shallow-land burial sites (open access)

Decommissioning of commercial shallow-land burial sites

Estimated costs and safety considerations for decommissioning LLW burial grounds have been evaluated. Calculations are based on a generic burial ground assumed to be located at a western and an eastern site. Decommissioning modes include: (1) site stabilization followed by long-term care of the site; and (2) waste relocation. Site stabilization is estimated to cost from $0.4 million to $7.5 million, depending on the site and the stabilization option chosen. Long-term care is estimated to cost about $100,000 annually, with somewhat higher costs during early years because of increased site maintenance and environmental monitoring requirements. Long-term care is required until the site is released for unrestricted public use. Occupational and public safety impacts of site stabilization and long-term care are estimated to be small. Relocation of all the waste from a reference burial ground is estimated to cost more than $1.4 billion and to require more than 20 years for completion. Over 90% of the cost is associated with packaging, transportation, and offsite disposal of the exhumed waste. Waste relocation results in significant radiation exposure to decommissioning workers.
Date: January 1, 1979
Creator: Murphy, E. S. & Holter, G. M.
Object Type: Article
System: The UNT Digital Library
Long-term leaching of irradiated spent fuel (open access)

Long-term leaching of irradiated spent fuel

Spent Light Water Reactor (LWR) fuel with burnups of 9, 28 and 54 MWd/kg U were leach tested at 25/sup 0/C in deionized water in a Paige apparatus. No discernible differences in leach rates were observed due to burnup. Additionally, the 28 MWd/kg U fuel was IAEA leach tested in five different leachants using the IAEA method. Deionized water gave the highest leach rates and a calcium chloride solution gave the lowest leach rates. An accelerated leaching period was observed during the Paige leach test of the 54 MWd/kg U spent fuel. Comparison between spent fuel and borosilicate waste glass leach rates was made. In sodium bicarbonate solution the leach rates are near equal and the glass becomes increasingly more durable with CaCl/sub 2/ solution, followed by sodium chloride solution, WIPP B brine and deionized water where the glass is two to three orders of magnitude more leach resistant than spent fuel. 16 figures.
Date: January 1, 1979
Creator: Katayama, Y. B. & Bradley, D. J.
Object Type: Article
System: The UNT Digital Library
Experimental process system development unit for producing semiconductor-grade silicon using the silane-to-silicon process. Quarterly progress report, October-December 1979 (open access)

Experimental process system development unit for producing semiconductor-grade silicon using the silane-to-silicon process. Quarterly progress report, October-December 1979

This program consists of the engineering design, fabrication, assembly, operation, economic analysis, and process support R and D for an Experimental Process System Development Unit (EPSDU). EPSDU equipment specification, vendor development, and evaluation of quotations represent a significant effort which will permit the start of ordering EPSDU equipment during the next quarter. Initial mini-burner test results are encouraging. It appears that a fairly simple and cost-effective waste treatment system may be possible. Engineering design packages such as the P and I, electrical one-line, and layout are also progressing well. The free-space reactor PDU was assembled and is undergoing checkout. The modified seal and shaft of the reactor scraper ran with limited success. A computer modeling of the PDU has been prepared using a two-dimensional axisymmetric model with recirculation. Some test runs have been made. Work on determination of the critical silane decomposition in a fixed bed has been completed. The data generated follow the extension of the Murthy's data. This data, along with the deposition rate data to be acquired, will be used in the fluid-bed reactor design. Present test data show that capacitive heating of the fluid bed and particle separation in a boot are very promising.
Date: January 1, 1979
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Development of an extended-burnup Mark B design. First semi-annual progress report, July-December 1978. Report BAW-1532-1. [PWR] (open access)

Development of an extended-burnup Mark B design. First semi-annual progress report, July-December 1978. Report BAW-1532-1. [PWR]

The primary objective of this program is to develop and demonstrate an improved PWR fuel assembly design capable of batch average burnups of 45,000-50,000 MWd/mtU. To accomplish this, a number of technical areas must be investigated to verify acceptable extended-burnup fuel performance. This report is the first semi-annual progress report for the program, and it describes work performed during the July-December 1978 time period. Efforts during this period included the definition of a preliminary design for a high-burnup fuel rod, physics analyses of extended-burnup fuel cycles, studies of the physics characteristics of changes in fuel assembly metal-to-water ratios, and development of a design concept for post-irradiation examination equipment to be utilized in examining high-burnup lead-test assemblies.
Date: October 1, 1979
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Exploding the myths about the fast breeder reactor (open access)

Exploding the myths about the fast breeder reactor

This paper discusses the facts and figures about the effects of conservation policies, the benefits of the Clinch River Breeder Reactor demonstration plant, the feasibility of nuclear weapons manufacture from reactor-grade plutonium, diversion of plutonium from nuclear plants, radioactive waste disposal, and the toxicity of plutonium. The paper concludes that the U.S. is not proceeding with a high confidence strategy for breeder development because of a variety of false assumptions.
Date: January 1, 1979
Creator: Burns, S.
Object Type: Article
System: The UNT Digital Library
Economic impact of using nonmetallic materials in low to intermediate temperature geothermal well construction. Volume 1 (open access)

Economic impact of using nonmetallic materials in low to intermediate temperature geothermal well construction. Volume 1

The results are presented of an exhaustive literature search and evaluation concerning the properties and economics of commercially available nonmetallic well casing and screens. These materials were studied in terms of their use in low to intermediate temperature geothermal well construction.
Date: December 1, 1979
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Industrial Fuel Gas Demonstration Plant Program. Procurement schedule for long-lead items (Deliverable No. 48) (open access)

Industrial Fuel Gas Demonstration Plant Program. Procurement schedule for long-lead items (Deliverable No. 48)

The long-lead items required for the Industrial Fuel Gas Demonstration Plant are given. Utilizing the Construction Plan (Deliverable No. 37), which is based upon 48 months to the completion of Phase II, the delivery requirements for each equipment item were determined. Required delivery dates were ascertained from the erection sequence for IFG Demonstration Plant units and equipment items. Lead times established by FWEC procurement personnel were then applied to arrive at a date when procurement action must be initiated. Procurement schedules for all equipment items are included in this document. Also evaluated were the activities required prior to actual placement of the order. Appropriate time has been included at the front end for receipt of vendor quotes, evaluation, and the recommendation for award to DOE and DOE approval (if required). The first milestone indicated on these schedules is the issuance of bid packages to prospective vendors. This is the required month to begin procurement activities to maintain the program time table. Six items have been determined to be long-lead time procurement items. The complete engineering, drafting, and procurement schedules for such items can be determined by referring to respective equipment numbers on the enclosed schedules.
Date: January 1, 1979
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Divertor experiments in a toroidal plasma, with E x B drift due to an applied radial electric field (open access)

Divertor experiments in a toroidal plasma, with E x B drift due to an applied radial electric field

It is proposed that the E x B drift arising from an externally applied electric field could be used in a tokamak or other toroidal magnetic plasma confinement device to remove plasma and impurities from the region near the wall and reduce the amount of plasma striking the wall. This could either augment or replace a conventional magnetic field divertor. Among the possible advantages of this scheme are easy external control over the rate of removal of plasma, more rapid removal than the naturally occurring rate in a magnetic divertor, and simplification of construction if the magnetic divertor is eliminated. Results of several related experiments performed in the Wisconsin Levitated Octupole are presented.
Date: September 1, 1979
Creator: Strait, E.J.
Object Type: Report
System: The UNT Digital Library
Recycled used fluorescent light tube solar water heater. Final technical report (open access)

Recycled used fluorescent light tube solar water heater. Final technical report

A project to investigate methods that might be used to utilize old fluorescent light tubes as solar water heater components then to produce a booklet of instructions for others to use to construct their own water heaters is described. Various methods of opening, cleaning and shaping the ends of the tubes were attempted. The reflective material needed inside some of the heaters was mylar and worked quite well but the Btu gain was disappointing. There were problems with the cement used and epoxy resin was finally used. Two types of collectors using reflectors also used temperature differential thermostats and small pumps. One thermosyphon model used no reflectors nor tube length copper pipe; it produced more Btu's per day than either motorized model. Preliminary test data are included. It was found that for Guam at least, the reflector type collectors I developed would not produce hot enough water for absorption type refrigeration.
Date: January 1, 1979
Creator: Jaquette, F M
Object Type: Report
System: The UNT Digital Library
Computational complexity in multidimensional neutron transport theory calculations. Final report (open access)

Computational complexity in multidimensional neutron transport theory calculations. Final report

Research to establish a general method to assess the performance and reliability of computer codes for the numerical approximation of linear operators is reported. The neutron transport operator was chosen as model. The general approach to solving the error problem and the use of benchmarks are sketched. This report contains only a brief administrative summary; references are given to forty reports and publications that contain detailed information. (RWR)
Date: December 1, 1979
Creator: Bareiss, E. H.
Object Type: Report
System: The UNT Digital Library
Theoretical aspects of solid state reactions in a mixed particulate ensemble and kinetics of lead zirconate formation (open access)

Theoretical aspects of solid state reactions in a mixed particulate ensemble and kinetics of lead zirconate formation

A theoretical analysis was carried out to estimate the quasi-steady-state external mass transport by lattice, surface and gaseous diffusion in terms of the stereologically measurable microstructural parameters of a mixed powder compact. It was shown that the gaseous transport can be described by a single dimensionless quantity termed sublimation transport modulus. Using these equations, the relative importance of the alternate external transport modes can be evaluated. Experimental work determined the reaction isotherms for the formation of lead zirconate from yellow PbO and monoclinic zirconia between 710/sup 0/C to 810/sup 0/C for two zirconia size distributions. The larger zirconia showed diffusion controlled shrinking core kinetics up to about 90 percent reaction while the smaller zirconia indicated a diffusion controlled spherical growth of up to 85 percent reaction after an instantaneous nucleation at a limited number of sites. The difference was attributed to the differences in the mixing time and not to the particulate sizes. It was observed that for the same size range, a longer mixing operation gave a better dispersion of reactants which resulted in a higher nucleation site density required for a shrinking core type of product morphology and faster kinetics. A microprobe profile analysis of partially reacted particles …
Date: September 1, 1979
Creator: Chandratreya, S.S.
Object Type: Report
System: The UNT Digital Library
Review of Gaussian diffusion-deposition models (open access)

Review of Gaussian diffusion-deposition models

The assumptions and predictions of several Gaussian diffusion-deposition models are compared. A simple correction to the Chamberlain source depletion model is shown to predict ground-level airborne concentrations and dry deposition fluxes in close agreement with the exact solution of Horst.
Date: January 1, 1979
Creator: Horst, T.W.
Object Type: Article
System: The UNT Digital Library
Evaluation of the solar building, Albuquerque, New Mexico. Final report, April 1974-September 1978 (open access)

Evaluation of the solar building, Albuquerque, New Mexico. Final report, April 1974-September 1978

During portions of the 1974-1975 and 1975-1976 winter heating seasons, a field evaluation was made of a solar-assisted heat pump heating system in a small commercial office building in Albuquerque, N.M. The system was comprised of one main water-to-water heat pump and five small water-to-air heat pumps. The liquid-type solar collector array had an area equivalent to about 10% of the building floor area. Other than the ethylene glycol/water solution circulated through the solar collector array, water was used in all parts of the system, including three thermal energy storage tanks. Considerable information concerning this project has been disseminated through conferences, workshops, technical papers at professional society meetings, reports to the federal government and Master of Science theses, all of which are referenced in this report. The work done on this project over the period of the contract is summarized and pertinent information concerning the building, the solar-assisted heat pump system, data acquisition aspects, results, and conclusions are included.
Date: December 1, 1979
Creator: Gilman, S.F.
Object Type: Report
System: The UNT Digital Library
Detectors for radiation dosimetry (open access)

Detectors for radiation dosimetry

For our purposes in this review, we note the following points: (1) for charged particle detection, these counters can be filled with any noble gas-quenching gas mixture that produces satisfactory electrical signals; (2) neutron counters, in which the neutrons are detected by their interaction with the specific filling of the chamber to yield an ionizing particle, require special gas mixtures containing /sup 3/He or BF/sub 3/, an alternative approach is to coat the inner surface of the cathode with a boron or lithium compound; (3) proportional counters are used if there is any need to discriminate between different types of radiation incident on the chamber by the magnitude of the ionizing energy retained within the sensitive volume of the counter; (4) proportional counters can operate at higher speeds than Geiger counters, typically up to 10/sup 7/ cts/sec versus less than 10/sup 5//sec for the Geiger counters; and (5) Geiger counters produce very large uniform pulses which can be scaled by very simple electronics, hence, they are often used in survey meters and other portable monitoring instruments.
Date: September 1, 1979
Creator: Perez-Mendez, V.
Object Type: Article
System: The UNT Digital Library
Secondary defects in quenched platinum (open access)

Secondary defects in quenched platinum

The structure of secondary defects in two different platinum purities quenched under ultra high vacuum, has been studied by transmission electron microscopy. Faulted loops on (100) planes have been observed in both materials. In the less pure platinum, Pt B (but purer in terms of carbon content), the defects were observed after quenching, whereas in the purest one, Pt A (but less pure in terms of carbon content), the defects were formed after a long annealing. The Burgers vector of the loops formed after the quenching was a/3 <100> and for loops formed during long annealings, was a/2 <100>, apparently. It was found that in Pt B the loop density increased and the loop size decreased as the quenching temperature was lowered.The same effect was produced by increasing the carbon content by a small amount. The loop formation was totally inhibited by adding a larger amount of carbon and also when the quenching was performed in poor vacuum (approx. 0.01 torr) or in air. The defects can be interpreted as pure vacancy loops heterogeneously nucleated at carbon atom clusters or, as plate like precipitates of carbon atoms and vacancies formed by a co-precipitation mechanism. The discussion of the experimental results …
Date: November 1, 1979
Creator: Perez, M.I.
Object Type: Report
System: The UNT Digital Library
Development and evaluation of die and container materials. Final report (open access)

Development and evaluation of die and container materials. Final report

Specific compositions of high purity silicon aluminum oxynitride (Sialon) and silicon beryllium oxynitride (Sibeon) solid solutions are shown to be promising refractory materials for handling and manipulating solar grade silicon into silicon ribbon. Well controlled processing schedules were developed for fabricating high purity Sialon and Sibeon materials. Essentially the impurity content of the hot pressed ceramics was due only to impurities from the original starting powders. A ceramic shaping die was successfully formed by diamond machining of a hot pressed blank. Projected manufacturing cost estimate for 10/sup 5/ dies per year is $5.4 per die. Evaluation of the interaction of these materials in contact with molten silicon indicates that solid solutions based upon ..beta..-Si/sub 3/N/sub 4/ are more stable than those based on Si/sub 2/N/sub 2/O. Sibeon is more resistant to molten silicon attack than Sialon, and both materials should preferably be used in an inert atmosphere rather than under vacuum conditions. This is because removal of oxygen from the silicon melt as SiO enhances the dissolution of aluminum and beryllium. The wetting angles of these materials are low enough (37/sup 0/ for x = 0.75 ..beta..&#x27; Sialon and 49/sup 0/ for x = 0.35 Sibeon) for these materials to …
Date: May 1, 1979
Creator: unknown
Object Type: Report
System: The UNT Digital Library