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Alumina lapping abrasive study

Description: To achieve greater quality control over lapped finishes, the 3- and 0.3-..mu..m alumina abrasives used in rough and finish lapping were studied. The 3-..mu..m abrasive was found to actually average 5 to 10 ..mu..m. The particle size distribution of the 0.3-..mu..m abrasive could not be determined with sufficient accuracy. Recommendations for procurement, storage, dispensing, and mixing were made to provide increased abrasive uniformity and freedom from contamination.
Date: October 1, 1977
Creator: Wagner, R.D.
Partner: UNT Libraries Government Documents Department

Quality-assurance study of the special - purpose finite-element program - SPECTROM: I. Thermal, thermoelastic, and viscoelastic problems. [Comparison with MARC-CDC]

Description: This comparison study involves a preliminary verification of finite element calculations. The methodology of the comparison study consists of solving four example problems with both the SPECTROM finite element program and the MARC-CDC general purpose finite element program. The results show close agreement for all example problems.
Date: December 1, 1980
Creator: Wagner, R.A.
Partner: UNT Libraries Government Documents Department

Physics at 10/sup 34/ cm/sup -2/ s/sup -1/

Description: Most of the detector studies at Snowmass-84 have rightfully concentrated on detailed studies of individual interactions - their rates, signatures, and backgrounds. Depending on the physics and the detector components, there seems to be agreement that general-purpose detectors will likely be able to accept luminosities up to 10/sup 32 -33/ cm/sup -2/ s/sup -1/. The purpose of this paper is to show how the physics reach of the SSC is extended by going to a luminosity of 10/sup 34/ cm/sup -2/ s/sup -1/, to take a first look at what sort of detector could be used at this luminosity, and to discuss how one might trigger on interesting events in the presence of many overlapping minimum bias events. We will assume that the SSC turns on at 10/sup 31/ or 10/sup 32/ cm/sup -2/ s/sup -1/, with an increase of luminosity to 10/sup 33/ over a period of a few years as the machine and detectors become better understood. Thus, the lower mass scale will have been explored and we can set our thresholds high when running 10/sup 34/.
Date: January 1, 1984
Creator: Diebold, R. & Wagner, R.
Partner: UNT Libraries Government Documents Department

The Hydrolysis Products of Tributyl Phosphate and Their Effect on the Tributyl Phosphate Process for Uranium Recovery

Description: A study was made of the stability of tributyl phosphate (TBP) to acids, bases, and UO/sub 2/(NO/sub 3/su)/sub 2/ solutions, and of the chemistry of its decomposition products. The effect of such decomposition products on the extraction behavior of ion of MBP and lines the RAW analyzer and a subsequent reduction of feed flow rate in each case resulted in immediate reduction in losses, as evidenced by the polarographic results. In many such instances, several hours of operation at high waste losses were avoided. A dropping mercury electrode was used for stream analysis, and the RAW solution was analyzed directiy without either dilution or addition of supporting eleclrolyte. Removal of dissolved oxygen and control of temperature were urnecessary. The precision of the method was better than plus or minus 5%, and the accuracy, which is dependent on calibration with a standard solution, was well within the precision value. The calibration curve is linear, for practical purposes, up to approximately 8 g/l UNH or 0.032 lb/gal uranium. (auth)
Date: April 15, 1951
Creator: Wagner, R. M.
Partner: UNT Libraries Government Documents Department

PREPARATION AND CONSOLIDATION OF THORIUM AND THORIUM HYDRIDE POWDERS

Description: A study was made of powder characteristics and cold compacting properties of metallic thorium, Th/sub 2/ and Th/sub 4/ powders produced from Annes billet lathe turnings. In addition a preliminary study was made of the influence of various powder processing and sintering variables on some physical properties of cold compacted bodies. The cold compacting and sintering characteristics of metallic thorium powder were generally superior to those ot the hydride powders. The thorium powder could be cold compacted at 75 tsi to 96% of theoretical Annes billet density and sintered to 99% of the billet density when heated to above 1250 deg C for one-half hour. A test bar made from cold compacted and sintered thorium powder was found to have an ultimate tensile strength of 45,200 psi and an area reduction of 38.5%. (auth)
Date: August 1, 1954
Creator: Wagner, R.B. & Storchheim, S.
Partner: UNT Libraries Government Documents Department

Continuous Fiber Ceramic Composites (CFCC)

Description: This report summarizes work to develop CFCC's for various applications in the Industries of the Future (IOF) and power generation areas. Performance requirements range from relatively modest for hot gas filters to severe for turbine combustor liners and infrared burners. The McDermott Technology Inc. (MTI) CFCC program focused on oxide/oxide composite systems because they are known to be stable in the application environments of interest. The work is broadly focused on dense and porous composite systems depending on the specific application. Dense composites were targeted at corrosion resistant components, molten aluminum handling components and gas turbine combustor liners. The development work on dense composites led to significant advances in fiber coatings for oxide fibers and matrix densification. Additionally, a one-step fabrication process was developed to produce low cost composite components. The program also supported key developments in advanced oxide fibers that resulted in an improved version of Nextel 610 fiber (commercially available as Nextel 650) and significant progress in the development of a YAG/alumina fiber. Porous composite development focused on the vacuum winding process used to produce hot gas filters and infrared burner components.
Date: December 18, 2002
Creator: Wagner, R. A.
Partner: UNT Libraries Government Documents Department

SOME EFFECTS OF RADIATION ON SOLVENT EXTRACTION PROCESSES

Description: Presented at the 135th National Meeting of the A.C.S., Boston, April 5- 10, 1959. The yield of total acid, G/sub acid/, in the radiolysis of tributyl phosphate--Amsco 125-82 solutions is 2.7 times the electron fraction of TBP, or approximately 2.7 times the weight fraction of TBP, per 100 ev of energy absorbed by the solution. Dibutyl phosphoric acid, DBPA, constitutes about 85% of the acid. Radiolysis of TBP also results in the conversion of about 0.9 molecules of TBP to a polymer per 100 ev of energy absorbed. Uranium extraction-stripping tests with an 8 stage spinner column have shown that one mole of uranium is retained in the organic phase during the stripping operation per mole of DBPA added prior to the extraction operation. This is at least twice as much uranium as would be expected on the basis of a compound of the composition UO/sub 2/(DBP)/ sub 2/. On the basis of a tentative molecular weight of 843 g/mole, the polymer retains in the organic phase during stripping operations about 1.2 moles of uranium per mole of polymer added prior to extraction. In additioo to polymer and acids, condensed phase radiolysis products include olefins, whose yield, expressed as G/sub c=c/, or number of double bonds formed per 100 ev of energy absorbed, decreases from ca 4 to 1 as the TBP concentration increases from 4.5 to 100 wt.%. Among newer extractants being examined for use in radiochemical reprocessing, diethyl carbonate, DEC, has been tested for uranium retention and fission product decontamination properties. After irradiation to the 400 watt-hr/ liter level, the uranium retention by DEC on stripping is decreased, rather than increased. Although gamma -decontamination was adversely affected, BETA - decontamination was essentially unaffected by irradiation to this level. (auth)
Date: January 26, 1959
Creator: Davis, W. Jr. & Wagner, R.M.
Partner: UNT Libraries Government Documents Department

SOME EFFECTS OF RADIATION ON SOLVENT EXTRACTION PROCESSES

Description: The yield of total acid, G/sub acid/, in the radiolysis of tributyl phosphate-Amsco 125-82 solutions is 2.7 times the electron fraction of TBP, or approximately 2.7 times the weight fraction of TBP, per 100 ev of energy absorbed by the solution. Dibutyl phosphoric acid, DBPA, constitutes about 85% of the acid. Radiolysis of TBP also results in the conversion of abcut 0.9 molecules of TBP to a polymer per 100 ev of energy absorbed. Uranium extraction-stripping tests with an 8 stage spinner column have shown that one mole of uranium is retained in the organic phase during the stripping operation per mole of DBPA added pnior to the extraction operation. On the basis of a tentative molecular weight of 848 g/mole, the polymer retains in the organic phase during stripping operations about 1.2 moles of uranium per mole of polymer added prior to extraction. In addition to polymer and acids, condensed phase radiolysis prcducts include olefins, whose yield, expressed as G/sub c=c/, or number of double bonds formed per 100 ev of energy absorbed, decreases from ca 4 to 1 as the TBP concentration increases from 4.5 to 100 wt.%. Diethyl carbcnate (DEC) was tested for uranium retention and fission product decontamination properties. After irradiation to the 400 watt-hr/liter level, the uranium retention by DEC on stripping is decreased, rather than increased. Although -decontamination was adversely affected, ore resistant t -decontamination was essentially unaffected by irradiation to this level. (auth)
Date: January 26, 1959
Creator: Davis, W. Jr. & Wagner, R.M.
Partner: UNT Libraries Government Documents Department

Novel oxide-oxide fiber reinforced hot gas filter development

Description: The objective of this program is to fabricate and test oxide fiber reinforced composite hot gas filter elements for advanced power generation systems. The level of mechanical durability exhibited by the currently available filters in field tests indicates that more rugged filters are required to meet the demands of large power generation systems. Furthermore, long term corrosion resistance of currently available filters has yet to be demonstrated in PFBC systems. The essential requirements of a composite material designed to meet the program objective for a toughened hot gas filter include the following: Stable continuous fiber; rigid porous matrix; engineered fiber-matrix interface; and cost effectiveness. Based on properties, availability, and cost, Mitsui`s ALMAX alumina fiber and 3M`s NEXTEL 610 alumina fiber were selected as the oxide reinforcement fibers. In order to meet the economic goals of the program it is essential that the cost and amount of continuous fiber be minimized. A four axis filament winder will be used to fabricate filter Preforms in a variety of fiber architectures. Carbon was used as the initial fiber coating because it was known to be resistant to the Processing chemicals. The coating was produced by pyrolysis of the resin based sizings on the continuous fibers. The matrix of the composite filter is comprised of chopped ceramic fiber. Saffil fiber was used for all compositions in this program.
Date: December 1, 1995
Creator: Wagner, R.A.
Partner: UNT Libraries Government Documents Department

RE/SPEC Inc. technical support to the Repository Technology Program; Summary of activities for September 1, 1988--June 30, 1992

Description: This report presents a summary of all RE/SPEC Inc. technical support activities to the Repository Technology Program (RTP) from September 1, 1988, through June 30, 1992. The RE/SPEC Inc. activities are grouped into the following categories: project management, project quality assurance (QA), performance assessment (PA), support of the Office of Civilian Radioactive Waste Management (OCRWM) through technical reviews and general assistance, participation in the Department of Energy (DOE) International Program, and code evaluation and documentation.
Date: June 1, 1992
Creator: Wagner, R.A.
Partner: UNT Libraries Government Documents Department

Near Field Environment Process Model Report

Description: Waste emplacement and activities associated with construction of a repository system potentially will change environmental conditions within the repository system. These environmental changes principally result from heat generated by the decay of the radioactive waste, which elevates temperatures within the repository system. Elevated temperatures affect distribution of water, increase kinetic rates of geochemical processes, and cause stresses to change in magnitude and orientation from the stresses resulting from the overlying rock and from underground construction activities. The recognition of this evolving environment has been reflected in activities, studies and discussions generally associated with what has been termed the Near-Field Environment (NFE). The NFE interacts directly with waste packages and engineered barriers as well as potentially changing the fluid composition and flow conditions within the mountain. As such, the NFE defines the environment for assessing the performance of a potential Monitored Geologic Repository at Yucca Mountain, Nevada. The NFe evolves over time, and therefore is not amenable to direct characterization or measurement in the ambient system. Analysis or assessment of the NFE must rely upon projections based on tests and models that encompass the long-term processes of the evolution of this environment. This NFE Process Model Report (PMR) describes the analyses and modeling based on current understanding of the evolution of the near-field within the rock mass extending outward from the drift wall.
Date: November 14, 2000
Creator: Wagner, R.A.
Partner: UNT Libraries Government Documents Department

High-Strength Zirconium Alloys

Description: The properties of zirconium alloyed with aluminum tin, and molybdenum were investigated. Using reactorgrade zirconium sponge, 11 zirconium-base alloys were double arc-melted and cast into 6-in.-diam. ingots weighing 35 lb each. By such standard hot working procedures as extruding and rolling, the ingots were converted to 1/8-in.-thick strips. The extruded and rolled products were used for a variety of evaluation studies which included corrosion thermal conductivity, tensile, and creep tests. The alloys demonstrated short-time elevated temperature strength properties equal to or greater than type-304 stainless steel. Their corrosion resistance in sodium, at 1000 deg F, compares favorable with that of unalloyed zirconium. The creep resistance and the thermal conductivity were found to be less than those for type-304 stainless steel, but adequate for nuclear reactor application. (auth)
Date: July 15, 1959
Creator: Wagner, R.K. & Kline, H.E.
Partner: UNT Libraries Government Documents Department

Superconducting thin film vertex detector for SSC (Superconducting Super Collider) applications

Description: A possibly very-radiation-hard detector based on superconducting thin film strips is described. The interaction of the thin film detector with charged particles is discussed, and the feasibility of extending previous work on alpha-particle detection to the more stringent requirements for minimum ionizing particles is considered. A novel approach to the readout is briefly outlined which utilizes the slow phase velocity of electromagnetic waves possible in superconducting waveguides. (LEW)
Date: January 1, 1987
Creator: Wagner, R.G. & Gray, K.E.
Partner: UNT Libraries Government Documents Department

Fabrication of tungsten--uranium dioxide honeycomb structures. Final report for period ending June 30, 1965

Description: Declassified 28 Aug 1973. Honeycomb structures in which uranium dioxide is dispersed in a tungsten matrix were made by two fabrication methods. These are discussed in detail and photographs of units produced by both methods are included. Several sizes of uranium dioxide powder were investigated as possible fuel materials. (73 figures, 25 tables) (auth)
Date: November 1, 1964
Creator: Foley, E.M.; Wagner, R.L. & White, D.E.
Partner: UNT Libraries Government Documents Department

Fabrication of tungsten--uranium dioxide honeycomb structures. Phase II. Quarterly report for period ending March 15, 1965

Description: Declassified 28 Aug 1973. Emphasis was given to the use of tungsten- clad uranium dioxide particles instead of surface cladding to reduce fuel loss during the fabrication and the high-temperature operation of tungsten-uranium dioxide reactor fuel elements. Two fabrication methods were investigated. ln one method individual unsintered hexagonal tubes were stacked, isostatically pressed, and sintered. The other method formed the entire unsintered honeycomb as a untt which was then sintered. Current emphasis is directed toward the latter method which eliminates problems of tube joining and inspection. Results of initial tests of equipment for direct forming of a 163-channel honeycomb with uniform fuel loading are described. (39 figures, 16 tables) (auth)
Date: May 21, 1965
Creator: Foley, E.M.; Wagner, R.L. & White, D.E.
Partner: UNT Libraries Government Documents Department

Comparison of the results of several heat transfer computer codes when applied to a hypothetical nuclear waste repository

Description: A direct comparison of transient thermal calculations was made with the heat transfer codes HEATING5, THAC-SIP-3D, ADINAT, SINDA, TRUMP, and TRANCO for a hypothetical nuclear waste repository. With the exception of TRUMP and SINDA (actually closer to the earlier CINDA3G version), the other codes agreed to within +-5% for the temperature rises as a function of time. The TRUMP results agreed within +-5% up to about 50 years, where the maximum temperature occurs, and then began an oscillary behavior with up to 25% deviations at longer times. This could have resulted from time steps that were too large or from some unknown system problems. The available version of the SINDA code was not compatible with the IBM compiler without using an alternative method for handling a variable thermal conductivity. The results were about 40% low, but a reasonable agreement was obtained by assuming a uniform thermal conductivity; however, a programming error was later discovered in the alternative method. Some work is required on the IBM version to make it compatible with the system and still use the recommended method of handling variable thermal conductivity. TRANCO can only be run as a 2-D model, and TRUMP and CINDA apparently required longer running times and did not agree in the 2-D case; therefore, only HEATING5, THAC-SIP-3D, and ADINAT were used for the 3-D model calculations. The codes agreed within +-5%; at distances of about 1 ft from the waste canister edge, temperature rises were also close to that predicted by the 3-D model.
Date: December 1, 1979
Creator: Claiborne, H.C.; Wagner, R.S. & Just, R.A.
Partner: UNT Libraries Government Documents Department

High Energy Physics Division. Semiannual report of research activities, January 1, 1995--June 30, 1995

Description: This report describes the research conducted in the High Energy Physics Division of Argonne National Laboratory during the period of January 1, 1995-July 31, 1995. Topics covered here include experimental and theoretical particle physics, advanced accelerator physics, detector development, and experimental facilities research. Lists of division publications and colloquia are included.
Date: December 1, 1995
Creator: Wagner, R.; Schoessow, P. & Talaga, R.
Partner: UNT Libraries Government Documents Department