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  Partner: UNT Libraries Government Documents Department
 Decade: 1970-1979
Hydrogen Isotope Permeation In Elastomeric Materials

Hydrogen Isotope Permeation In Elastomeric Materials

Date: March 1, 1976
Creator: Steinmeyer, R. H. & Braun, J. D.
Description: The permeabilities of elastomeric and polymeric materials to hydrogen isotopes were measured at room temperature. The technique for measuring permeation rates is based on the following constant-volume method: a fixed pressure of gas is applied to one side of the specimen to be studied and the permeability constant is determined from the observed rate of pressure increase in an initially evacuated volume on the other side of the specimen. Permeability constants for hydrogen, deuterium, and tritium were measured for Mylar, Teflon, Kapton, Saran, Buna-N, and latex rubber. Results were compared with literature values for hydrogen and deuterium where available and showed excellent agreement.
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Corrosion Considerations in the Use of Boral in Spent Fuel Storage Pool Racks

Corrosion Considerations in the Use of Boral in Spent Fuel Storage Pool Racks

Date: February 22, 1979
Creator: Weeks,J.R.
Description: Boral is a cermet of Boron Carbide 'B{sub 4}C' in aluminum clad in aluminum. It is manufactured in rolled sheets using techniques similar to those used in the production of uranium aluminum fuel elements. The core of the standard Boral contains 35% boron carbide by weight. Cladding material is typical 1100 aluminum. Where it is exposed to water in service, the edges of the Boral are recommended by the manufacturer to be clad with aluminum by welding. In Spent Fuel Pool (SFP) racks, the Boral is usually not a structural member but is inserted in cavities between the spent fuel storage positions in the racks. In these locations it is sealed by welding to prevent access of water. Inherently, however, the corrosion of the Boral, both the boron carbide-aluminum cermet and the aluminum cladding, should be minimal in a spent fuel storage pool. The cavities into which the Boral is sealed are typically fabricated of aluminum alloys, i.e. type 6061, or stainless steel. In either case, these are the structural members of the SFP racks. In an SFP, water chemistry tends to be strictly controlled because the SFP water mixes with the reactor coolant during refueling procedures. In SFP's at ...
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Second Annual AEC Scientific Computer Information Exhange Meeting. Proceedings of the technical program theme: computer graphics

Second Annual AEC Scientific Computer Information Exhange Meeting. Proceedings of the technical program theme: computer graphics

Date: January 1, 1974
Creator: Peskin,A.M. & Shimamoto, Y.
Description: The topic of computer graphics serves well to illustrate that AEC affiliated scientific computing installations are well represented in the forefront of computing science activities. The participant response to the technical program was overwhelming--both in number of contributions and quality of the work described. Session I, entitled Advanced Systems, contains presentations describing systems that contain features not generally found in graphics facilities. These features can be roughly classified as extensions of standard two-dimensional monochromatic imaging to higher dimensions including color and time as well as multidimensional metrics. Session II presents seven diverse applications ranging from high energy physics to medicine. Session III describes a number of important developments in establishing facilities, techniques and enhancements in the computer graphics area. Although an attempt was made to schedule as many of these worthwhile presentations as possible, it appeared impossible to do so given the scheduling constraints of the meeting. A number of prospective presenters 'came to the rescue' by graciously withdrawing from the sessions. Some of their abstracts have been included in the Proceedings.
Contributing Partner: UNT Libraries Government Documents Department
Heat Transfer Correlation for Finned Casks

Heat Transfer Correlation for Finned Casks

Date: April 1, 1974
Creator: Griffin, J. F.
Description: Design of finned casks for dissipation of heat from radioactive decay usually requires reliance on generalized correlations in the literature which do not necessarily apply to the specific cask design. A correlation was developed, based on temperature profile measurements, for the design of upright cylindrical casks with vertical fins for convective and radiant heat transfer to ambient air. Temperature data at various heat loads were obtained for two different cask sizes of the same basic design. Each cask is mounted on a steel pallet and contained within a steel mesh cage. The smaller cask, which has 23 fins, has been approved (DOT-SP-6321) for shipment of up to 1400 W (th), and approval is being obtained (AEC AL USA/9503 BLF) for shipment of up to 3500 W heat load in the larger, 60-fin cask. The applicable theoretical equations were fit to the temperature data for both casks by simply adjusting the value used for the number of fins. The resulting correlation provides a reliable method for interpolation and extrapolation and for design of similar finned casks.
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SELECTION OF PROCESS PARAMETERS FOR SODIUM REMOVAL VIA THE WATER VAPOR NITROGEN PROCESS

SELECTION OF PROCESS PARAMETERS FOR SODIUM REMOVAL VIA THE WATER VAPOR NITROGEN PROCESS

Date: November 15, 1977
Creator: M, CRIPPEN
Description: This report reviews the water vapor nitrogen (WVN) process for removing sodium from stainless steel equipment, with emphasis on the basis for selecting final operating parameters. the process includes vapor treatment with 5% water at 160 F to 190 F, hot water rinsing, and hot gas drying.
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Hydrogen Isotope Separation System for the Tokamak Experimental Power Reactor

Hydrogen Isotope Separation System for the Tokamak Experimental Power Reactor

Date: March 1, 1976
Creator: Wilkes, W. R.
Description: An isotopic separation system for processing the fuel in the Tokamak Experimental Power Reactor is described. Two cryogenic distillation columns are used in sequence to recover 80% of the hydrogen from a fuel mixture originally containing equal parts of deuterium and tritium with a 1% hydrogen impurity. The hydrogen thus removed contains less than 1/2% tritium, which may be recovered in a separate system designed for that purpose. It is assumed that separation of the deuterium and the tritium is not required. A total tritium inventory of approximately 38,000 Ci (3.8 g) is projected.
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The Uranium-Tritium System - The Storage of Tritium

The Uranium-Tritium System - The Storage of Tritium

Date: March 1, 1976
Creator: Carlson, R. S.
Description: The thermodynamics of the uranium-tritium system were determined over the pressure range of 2 x 10 to the minus 4 to 20 atm from experimental composition-pressure-temperature data. Both enthalpy and entropy were shown to vary slightly with composition by analysis of van't Hoff plots for the U-D system and the U-T system. The evolution of helium-3 borne in the lattice of a fully tritiated sample of uranium was studied over a period of several months, and the relative proportion of helium-3 and tritium in the evolved gas from an aged UT3 sample was determined at several temperatures. The desorption and absorption characteristics of a typical uranium-tritium storage bed have been studied and observed for several years.
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Mound Laboratory Plutonium-238 Study Off-Site Analytical Data May-December 1974

Mound Laboratory Plutonium-238 Study Off-Site Analytical Data May-December 1974

Date: March 1, 1975
Creator: Robinson, Bob; Rogers, D. R.; Westendorf, W. H. & Black, H. A.
Description: Preliminary samples collected from off-site sediment in the Miami-Erie Canal Area near Mound Laboratory indicated that plutonium-238 concentrations are substantially above baseline levels. As a result an extensive sampling and analysis program was performed to determine the plutonium-238 concentrations as a function of depth and location in a drainage ditch, the canal, two ponds, a run-off hollow, a canal overflow creek and the Great Miami River. The plutonium-238 concentration data was used to estimate the total inventory of 238Pu deposited in these waterways, to determine the extent of the contamination, and to evaluate the potential health hazards to the general population of the area. The scope of this report is to present the data collected during this study. Detailed interpretation of the data will be presented in subsequent reports.
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Reference Documents for the Proposal for a NATIONAL SYNCHROTRON LIGHT SOURCE

Reference Documents for the Proposal for a NATIONAL SYNCHROTRON LIGHT SOURCE

Date: April 16, 1976
Creator: Blewett,J.P.
Description: The spectra, angular distribution and polarization functions of synchrotron radiation are tabulated in parametric form. Numerous graphs of the functions are included which can be used for rapid estimation of photon flux as a function of the various parameters. The extended synchrotron radiation source is described and the exact, but unintegrable, equations are derived. Properties of this source depend upon at least nine parameters. An approximation of the source accurate enough for estimating flux in optical instruments is developed. Power and power density in the radiation beam are described and convenient approximations are developed. Simple optical transformations are used to illustrate some of the important properties of the extended source. Also included are: (1) a brief description and short table of the Bessel functions used; (2) an outline of the properties of electron orbits in a storage ring; and (3) a description and short table of integrating function ef(a,Y).
Contributing Partner: UNT Libraries Government Documents Department
Instrumentation for Environmental Monitoring--Radiation--Vol3Pt2

Instrumentation for Environmental Monitoring--Radiation--Vol3Pt2

Date: September 1, 1979
Creator: Authors, Various
Description: No abstract prepared.
Contributing Partner: UNT Libraries Government Documents Department
AN INVESTIGATION OF METALLURGICAL FACTORS WHICH AFFECT THE FRACTURE TOUGHNESS OF ULTRA HIGH STRENGTH STEELS

AN INVESTIGATION OF METALLURGICAL FACTORS WHICH AFFECT THE FRACTURE TOUGHNESS OF ULTRA HIGH STRENGTH STEELS

Date: May 1, 1973
Creator: Wood, William E.; Parker, Earl R. & Zackay, Victor F.
Description: The relationship between microstructure, heat treatment and room temperature fracture toughness has been determined for the low alloy ultra-high strength steels 4130, 4330, 4340, 4140 and 300-M. Optical metallography, microprobe analysis, and scanning electron microscopy were used to characterize the structure and morphology, while both Charpy V-notch impact tests and plane strain fracture toughness tests were used to determine the fracture properties. The normal commercial heat treatment resulted in the formation of some bainite in all the alloys. MnS inclusions on prior austenite grain boundaries were found to initiate cracks during loading. By increasing the austenitizing temperature to l200 C, the fracture toughness could be increased by at least 60%. For some alloys increasing the severity of the quench in conjunction with the higher austenitizing temperatures resulted in further increases in the fracture toughness, and the elimination of any observable upper bainite. There was no correlation between the Charpy impact test results and the fracture toughness results. The alloys 4130, 4140, 4340 all showed a severe intergranular embrittlement when austenitized at high temperatures and tempered above 200 C, while the alloys 4330 and 300-M exhibited no drop in toughness for the same heat treatment conditions. The as-quenched tensile specimens had ...
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ISOTOPE PRODUCTION CROSS SECTIONS FROM THE FRAGMENTATION OF 16O AND 12C AT RELATIVISTIC ENERGIES

ISOTOPE PRODUCTION CROSS SECTIONS FROM THE FRAGMENTATION OF 16O AND 12C AT RELATIVISTIC ENERGIES

Date: February 1, 1975
Creator: Lindstrom, P.J.; Greiner, D.E.; Heckman, H.H.; Cork, Bruce & Bieser, F.S.
Description: The 0-degree fragmentation products of {sup 16}O and {sup 12}C at 2.1-GeV/n and {sup 12}C at 1.05-GeV/n have been measured for targets ranging from H to Pb. They present a total of 464 partial-production cross sections for 35 isotopes. The cross sections are energy independent and can be factored into beam-fragment and target terms. The target factor, {gamma}{sub T} = A{sub T}{sup 1/4}, and other evidence, imply the isotopes are produced in peripheral interactions.
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MULTIPERIPHERAL MODEL WITH PSEUDOSCALAR AND VECTOR MESON EXCHANGE

MULTIPERIPHERAL MODEL WITH PSEUDOSCALAR AND VECTOR MESON EXCHANGE

Date: September 1, 1972
Creator: Avalos, Daniel R. & Sorensen, Cristian.
Description: Previous work on generalizations of the ABFST multiperipheral model is extended to allow for vector meson exchange. The intercept of the Pomeranchon pole, the magnitude of asymptotic total cross sections and off-shell corrections to them are calculated.
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pi+p, pi+n, AND pi+d INTERACTIONS - A COMPILATION: PARTS I and II

pi+p, pi+n, AND pi+d INTERACTIONS - A COMPILATION: PARTS I and II

Date: May 1, 1973
Creator: Chew, D.M.; Henri, V.P.; Lasinski, T.A.; Trippe, T.G.; Uchiyama, F. & Windelmann, F.C.
Description: No abstract prepared.
Contributing Partner: UNT Libraries Government Documents Department
PHYTOPLANKTON AND BIOMASS DISTRIBUTION AT POTENTIAL OTEC SITES

PHYTOPLANKTON AND BIOMASS DISTRIBUTION AT POTENTIAL OTEC SITES

Date: June 1, 1979
Creator: Johnson, P.W. & Horne, A.J.
Description: Net or large phytoplankton species composition and most phytoplankton abundance was measured at three OTEC sites. In the Gulf of Mexico and Hawaii, diatoms dominated while the blue-green algae Trichodesmium was most common at Puerto Rico. The species ratio of diatoms to dinoflagellates was approximately 1:1. The species diversity varied from site to site, Hawaii > Puerto Rico > Gulf of Mexico. Chlorophyll a, which is a measure of the pigment of all algae size ranges, showed a subsurface peak of 0.14-0.4 g per liter at 75 to 125 m. Occasional surface peaks up to 0.4 pg per liter occurred. Further refinement of collection techniques is needed to delineate the subtle environmental effects expected by OTEC plant discharges.
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COMPARISON OF NUTRIENT DATA FROM FOUR POTENTIAL OTEC SITES

COMPARISON OF NUTRIENT DATA FROM FOUR POTENTIAL OTEC SITES

Date: June 1, 1979
Creator: Quinby-Hung, M.S.
Description: An in-progress assessment of nutrient chemical data (phosphate, nitrate, nitrite, and silicate) from four potential OTEC sites (Puerto Rico, the Gulf of Mexico, Hawaii, and the South Atlantic) show reasonable comparison with archival data. At this time sufficient data is available only at the Tampa site (Gulf of Mexico) to discern seasonal variations which show an influx of nutrient-rich water in February, which decreases with time to a minimum in December. Results show a greater potential for stimulation of primary productivity at the Hawaii site than in the northern Gulf of Mexico due to the discharge of the cold water pipe into the photic zone.
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COMPARISONS OF CODED APERTURE IMAGING USING VARIOUS APERTURES AND DECODING METHODS

COMPARISONS OF CODED APERTURE IMAGING USING VARIOUS APERTURES AND DECODING METHODS

Date: July 1, 1976
Creator: Chang, L.-T.; Macdonald, B. & Perez-Mendez, V.
Description: The utility of coded aperture imaging of radioisotope distributions in Nuclear Medicine is in its ability to give depth information about a three dimensional source. We have calculated imaging with Fresnel zone plate and multiple pinhole apertures to produce coded shadows and reconstruction of these shadows using correlation, Fresnel diffraction, and Fourier transform deconvolution. Comparisons of the coded apertures and decoding methods are made by evaluating their point response functions both for in-focus and out-of-focus image planes. Background averages and standard deviations were calculated. In some cases, background subtraction was made using combinations of two complementary apertures. Results using deconvolution reconstruction for finite numbers of events are also given.
Contributing Partner: UNT Libraries Government Documents Department
ENVIRONMENTAL MONITORING AND ASSESSMENT PROGRAM AT POTENTIAL OTEC SITES

ENVIRONMENTAL MONITORING AND ASSESSMENT PROGRAM AT POTENTIAL OTEC SITES

Date: June 1, 1979
Creator: Wilde, P.
Description: Ecologically sound operations of projected Ocean Thermal Energy Conversion (OTEC) plants can be insured by careful attention to the marine environment during the design phase. this requires quality information from regions of potential OTEC interest, coordinated with required assessment studies to insure legal compliance. Currently, preliminary or actual surveys and laboratory studies are being conducted in the waters of Puerto Rico, the Gulf of Mexico, Hawaii, and Guam for potential moored or seacoast OTEC plants and in the equatorial South Atlantic for proposed plant-ship operations to provide such benchmark and baseline data. These data plus existing archival information can be used to model effects of OTEC operations based on projected design schemes. Four major areas of concerns (1) redistribution of oceanic properties, (2) chemical pollution, (3) structural effects, and (4) socio-legal-economic; and 11 key issues associated with OTEC deployment and operation have been identified. In general mitigating strategies can be used to alleviate many deleterious environmental effects of operational problems as biostimulation, outgassing, etc. Various assessment research studies on toxicity, biocide releases, etc., are under way or are planned to investigate areas where no clear mitigating strategy is available. Data from the monitoring and assessment programs is being integrated into ...
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Calorimetric Assay Of Plutonium

Calorimetric Assay Of Plutonium

Date: May 1, 1977
Creator: Rodenburg, W. W.
Description: This report describes procedures for applying calorimetry for the control and accounting of plutonium. These procedures will be useful in establishing a measurement program to fulfill the regulatory requirements.
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Chemical Coagulation of Radioactive Wastes at High pH

Chemical Coagulation of Radioactive Wastes at High pH

Date: June 1, 1976
Creator: Koenst, J. W. & Blane, D. E.
Description: The waste treatment facility at Mound Laboratory was recently modified for the treatment of plutonium-bearing wastes. Prior to July 1, 1975, the facility had been run at pH 8.8; however, since the plant was modified it has been run at pH 11.3 with different chemical dosages. The improvement in effluent quality using the higher pH process (pH 11.3) has been dramatic. Prior to the changeover, the system effluent activity levels ranged from 2-3 dis/min/ml (9-14x10 to the minus 4 uCi/1) specific 238Pu; after the changeover effluent activity levels ranged from 0.3-0.5 dis/min/ml (1.4-2.3x10 to the minus 4 uCi/1) specific 238Pu. Total activity discharged (on a monthly basis) has been cut by more than a factor of 2, because of the changeover to the high pH process. Effluent levels are about as low as can be obtained in this type of waste treatment process.
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Absolute Glovebox Ventilation Filtration System with Unique Filter Replacement Feature

Absolute Glovebox Ventilation Filtration System with Unique Filter Replacement Feature

Date: December 31, 1975
Creator: Freeman, S. S. & Slusher, W. A.
Description: A glovebox ventilation system was designed for a new plutonium-238 processing facility that provided 1) downdraft ventilation, 2) a leak tight seal around the High Efficiency Particulate Air (HEPA) filters, and 3) a method for changing the filters internally without risk of contaminating the laboratory.
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THE MARINE MAMMAL FAUNA OF POTENTIAL OTEC SITES IN THE GULF OF MEXICO AND HAWAII

THE MARINE MAMMAL FAUNA OF POTENTIAL OTEC SITES IN THE GULF OF MEXICO AND HAWAII

Date: May 1, 1979
Creator: Payne, S.F.
Description: Twenty-seven marine mammal species have been recorded for the Gulf of Mexico, including 7 Mysticetes or baleen whales, 17 Odontocetes or toothed whales, 1 Sirenian (manatee), and 1 or 2 Pinnipeds or seals. The most common species in the Gulf is Tursiops truncatus, the bottlenosed dolphin, an inshore species. Offshore, Stenella plagiodon, the spotted dolphin, is fairly common. Most other species are recorded from very few sightings or strandings. None of the endangered species is common in potential OTEC sites in the Gulf of Mexico. Twenty-two marine mammals may occur in Hawaii; 2 Mystecetes, 19 Odonotocetes, and the endemic monk seal. The monk seal (Monachus schauinslandi), an endangered species, lives in the extreme northwestern island chain away from potential OTEC sites. Among the most common cetaceans in Hawaii is the endangered humpback whale (Megaptera novaeangliae). Stenella longirostris, the spinner dolphin; and Tursiops sp., the bottlenosed dolphin are also fairly common. The baleen whales feed on zooplankton during the summer in polar waters, and are migratory, while the toothed whales feed mainly on fish and squid, and are found in temperate or tropical regions year-round. The manatee is vegetarian and the pinnipeds are fish- or squid-eaters. Environmental effects of OTEC which ...
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LMFBR (LIQUID METAL FAST BREEDER REACTOR) READTION RATE AND DOSIMETRY 3RD QUARTERLY PROGRESS REPORT DECEMBER 1971 JANUARY FEBRUARY 1972

LMFBR (LIQUID METAL FAST BREEDER REACTOR) READTION RATE AND DOSIMETRY 3RD QUARTERLY PROGRESS REPORT DECEMBER 1971 JANUARY FEBRUARY 1972

Date: March 1, 1972
Creator: WN, MCELROY
Description: This report was compiled at the Hanford Engineering Development Laboratory operated by Westinghouse Hanford Company, a subsidiary of Westinghouse Electric Corporation, for the United States Atomic Energy Commission, Division of Reactor Development and Technology, under Contract No. AT (45-1) 2170. It describes technical progress made in the Interlaboratory LMFBR Reaction Rate Program during the reporting period. The Interlaboratory LMFBR Reaction Rate (ILRR) program has been established by USAEC/RDT to develop a capability to accurately measure neutron-induced reaction rates for LMFBR fuels and materials development programs. The initial goal for the principal fission reactions, {sup 235}U, {sup 238}U, and {sup 239}Pu, is an accuracy to within {+-}5 at the 95% confidence level. Accurate measurement of other fission and non-fission reactions will be required, but to a lesser accuracy, between {+-}5 to 10% at the 95% confidence level. A secondary program objective is improvement in knowledge of the nuclear parameters involved in fuels and materials dosimetry measurements of neutron flux, spectra, fluence, and burnup. These accuracy goals for the ILRR program are severe; measurements of fast-neutron-induced reaction rates have not been rapidly moving toward this level of precision. Using a number of techniques in well established neutron environments of current interest for ...
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LMFBR (LIQUID METAL FAST BREEDER REACTOR) REACTION RATE AND DOSIMETRY QUARTERLY PROGRESS REPORT JUNE JULY AUGUST 1971

LMFBR (LIQUID METAL FAST BREEDER REACTOR) REACTION RATE AND DOSIMETRY QUARTERLY PROGRESS REPORT JUNE JULY AUGUST 1971

Date: September 1, 1971
Creator: WN, MCELROY
Description: This report describes progress in the USAEC-sponsored Interlaboratory LMFBR Reaction Rate (ILRR) program. This program has been established by RDT to develop a capability to accurately measure neutron-induced reaction rates for LMFBR fuels and materials development programs. The initial goal for the principal fission reactions, {sup 235}U, {sup 238}U, and {sup 239}Pu, is an accuracy to within {+-} 5 at the 95% confidence level. Accurate measurement of other fission and non-fission reactions will be required, but to a lesser accuracy, between {+-} 5 to 10% at the 95% confidence level. A secondary program objective is improvement in knowledge of the nuclear parameters involved in fuels and materials dosimetry measurements of neutron flux, spectra, fluence, and burnup. The accuracy goals of the ILRR program are severe; measurements of fast-neutron-induced reaction rates have not been rapidly moving toward this level of precision. Using a number of techniques in well established neutron environments of current interest for fast reactor development and critically evaluating the results will help establish existing levels of accuracy and indicate the scale of effort required for improvement. To accomplish the objectives of this program, reliable and accepted experimental values of reaction rates and ratios will be determined for various ...
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