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2-Dimensional studies of the disk-and-washer and side-coupled resonant cavity structures (open access)

2-Dimensional studies of the disk-and-washer and side-coupled resonant cavity structures

The work done consists of three parts: optimizing the disk-and-washer (DAW) structure at ..beta.. = 0.5662 corresponding to E = 200 MeV; comparing the DAW structure with the side-coupled (SCS) structure at various values of beta, ranging from ..beta.. = 0.4569 and E = 116 MeV to ..beta.. = 0.7131 and E = 400 MeV; and re-optimizing the DAW structure at ..beta.. = 0.7131. 4 refs., 51 figs., 41 tabs.
Date: December 1, 1987
Creator: Larry, L.D. Jr.
Object Type: Report
System: The UNT Digital Library
300 Area Process Trench Sediment Analysis Report (open access)

300 Area Process Trench Sediment Analysis Report

This report describes the results of a sampling program for the sediments underlying the Process Trenches serving the 300 Area on the Hanford reservation. These Process Trenches were the subject of a Closure Plan submitted to the Washington State Department of Ecology and to the US Environmental Protection Agency in lieu of a Part B permit application on November 8, 1985. The closure plan described a proposed sampling plan for the underlying sediments and potential remedial actions to be determined by the sample analyses results. The results and proposed remedial action plan are presented and discussed in this report. 50 refs., 6 figs., 8 tabs.
Date: December 1, 1987
Creator: Zimmerman, M.G. & Kossik, C.D.
Object Type: Report
System: The UNT Digital Library
Absolute rate measurements of two-photon process of gases, liquids, and solids (open access)

Absolute rate measurements of two-photon process of gases, liquids, and solids

Due to rapid improvements in high-power laser performance, two-photon absorption processes have become a very useful tool for studying the molecular structures of various gases, liquids and solids. However, measurements of absolute two-photon absorption cross sections were more or less ignored previously because of their small size. In this work, we obtained not only the two-photon absorption spectra, but also measurements of their absolute cross sections for various gases, liquids, and solids. 8 refs., 1 fig., 1 tab.
Date: December 1, 1987
Creator: Chen, C.H.; McCann, M.P. & Payne, M.G.
Object Type: Article
System: The UNT Digital Library
Addendum to Microalgae Culture Collection 1986-1987 (open access)

Addendum to Microalgae Culture Collection 1986-1987

The SERI Microalgae Culture Collection was established in support of the U.S. Department of Energy Biofuels and Municipal Waste Technology Program to provide a repository for strains identified or developed for mass culture biomass production.
Date: December 1, 1987
Creator: Johansen, J. R.; Lemke, P.; Nagle, N. J.; Chelf, P.; Roessler, P. G.; Galloway, R. et al.
Object Type: Report
System: The UNT Digital Library
Advanced nuclear rocket engine mission analysis (open access)

Advanced nuclear rocket engine mission analysis

The use of a derivative of the NERVA engine developed from 1955 to 1973 was evluated for potential application to Air Force orbital transfer and maneuvering missions in the time period 1995 to 2020. The NERVA stge was found to have lower life cycle costs (LCC) than an advanced chemical stage for performing low earth orbit (LEO) to geosynchronous orbit (GEO0 missions at any level of activity greater than three missions per year. It had lower life cycle costs than a high performance nuclear electric engine at any level of LEO to GEO mission activity. An examination of all unmanned orbital transfer and maneuvering missions from the Space Transportation Architecture study (STAS 111-3) indicated a LCC advantage for the NERVA stage over the advanced chemical stage of fifteen million dollars. The cost advanced accured from both the orbital transfer and maneuvering missions. Parametric analyses showed that the specific impulse of the NERVA stage and the cost of delivering material to low earth orbit were the most significant factors in the LCC advantage over the chemical stage. Lower development costs and a higher thrust gave the NERVA engine an LCC advantage over the nuclear electric stage. An examination of technical data …
Date: December 1, 1987
Creator: Ramsthaler, J.; Farbman, G.; Sulmeisters, T.; Buden, D. & Harris, P.
Object Type: Article
System: The UNT Digital Library
Altus Times (Altus, Okla.), Vol. 65, No. 287, Ed. 1 Tuesday, December 1, 1987 (open access)

Altus Times (Altus, Okla.), Vol. 65, No. 287, Ed. 1 Tuesday, December 1, 1987

Daily newspaper from Altus, Oklahoma that includes local, state, and national news along with advertising.
Date: December 1, 1987
Creator: Lomenick, Rick
Object Type: Newspaper
System: The Gateway to Oklahoma History
Analysis of proposed gamma-ray detection system for the monitoring of core water inventory in a pressurized water reactor (open access)

Analysis of proposed gamma-ray detection system for the monitoring of core water inventory in a pressurized water reactor

An initial study has been performed of the feasibility of employing an axial array of gamma detectors located outside the pressure vessel to monitor the coolant in a PWR. A one-dimensional transport analysis model is developed for the LOFT research reactor and for a mock-PWR geometry. The gamma detector response to coolant voiding in the core and downcomer has been determined for both geometries. The effects of various conditions (for example, time after shutdown, materials in the transport path, and the relative void fraction in different water regions) on the detector response are studied. The calculational results have been validated by a favorable comparison with LOFT experimental data. Within the limitations and approximations considered in the analysis, the results indicate that the gamma-ray detection scheme is able to unambiguously respond to changes in the coolant inventory within any vessel water region.
Date: December 1, 1987
Creator: Markoff, Diane Melanie
Object Type: Report
System: The UNT Digital Library
Anisotropic yielding of rocks at high temperatures and pressures (open access)

Anisotropic yielding of rocks at high temperatures and pressures

Results to date are: All of the starting materials for the three year project have been collected. Included in our collection are relatively fine-grained, fresh, oriented blocks of schist, gneiss, and micaceous quartzite with well-defined foliations and lineations as well as granite blocks oriented with respect to the principal quarrying orientations, the rift, grain, and hardway. A suite of samples has also been collected from an exposed granite stock and surrounding country rocks in order to evaluate the strengths and distribution of fabrics which may be encountered while drilling. These fabrics appear to be directly related to the forceful emplacement of the pluton. The literature on the mechanics of intrusion has been reviewed with regard to strain gradients and foliation development associated with diapiric flow. This information will be used to evaluate flow of varying fabrics on yield criteria within and surrounding magma chambers. Twenty-three successful experiments have been performed on samples of gneiss cored along six different orientations at temperatures ranging from 25{degrees} to 700{degrees}C. These experiments include extension tests, unconfined compression tests, and compression tests performed at P{sub c} = 100 MPa. Theoretical yield conditions for anisotropic materials have been reviewed and the assumptions upon which they are …
Date: December 1, 1987
Creator: Kronenberg, A.K.; Russell, J.E.; Handin, J.; Gottschalk, R.R. & Shea, W.T.
Object Type: Report
System: The UNT Digital Library
Argonne National Laboratory 1986 publications (open access)

Argonne National Laboratory 1986 publications

This report is a bibliography of scientific and technical 1986 publications of Argonne National Laboratory. Some are ANL contributions to outside organizations' reports published in 1986. This compilation, prepared by the Technical Information Services Technical Publications Section (TPS), lists all nonrestricted 1986 publications submitted to TPS by the Laboratory's Divisions. Author indexes list ANL authors only. If a first author is not an ANL employee, an asterisk in the bibliographic citation indicates the first ANL author. The report is divided into seven parts: Journal Articles -- Listed by first author; ANL Reports -- Listed by report number; ANL and non-ANL Unnumbered Reports -- Listed by report number; Non-ANL Numbered Reports -- Listed by report number; Books and Book Chapters -- Listed by first author; Conference Papers -- Listed by first author; and Complete Author Index.
Date: December 1, 1987
Creator: Kopta, J.A. & Springer, C.J.
Object Type: Report
System: The UNT Digital Library
B Physics (open access)

B Physics

We review B physics and the motivation for studying B decays, including CP-violating effects in the B meson system. 33 refs., 20 figs.
Date: December 1, 1987
Creator: Gilman, Frederick J.
Object Type: Article
System: The UNT Digital Library
The Baytown Sun (Baytown, Tex.), Vol. 66, No. 27, Ed. 1 Tuesday, December 1, 1987 (open access)

The Baytown Sun (Baytown, Tex.), Vol. 66, No. 27, Ed. 1 Tuesday, December 1, 1987

Daily newspaper from Baytown, Texas that includes local, state, and national news along with advertising.
Date: December 1, 1987
Creator: Brown, Leon
Object Type: Newspaper
System: The Portal to Texas History
Biomass conversion Task 4 1988 program of work: International Energy Agency Bioenergy Agreement (open access)

Biomass conversion Task 4 1988 program of work: International Energy Agency Bioenergy Agreement

For biomass to meet its potential as an energy resource, conversion processes must be available which are both efficient and environmentally acceptable. Conversion can include direct production of heat and electricity as well as production of intermediate gaseous, liquid, and solid fuels. While many biomass conversion processes are commercially available at present, others are still in the conceptual stage. Additional research and development activities on these advanced concepts will be necessary to fully use biomass resources. Ongoing research on biomass conversion processes is being conducted by many nations throughout the world. In an effort to coordinate this research and improve information exchange, several countries have agreed to a cooperative effort through the International Energy Agency's Bioenergy Agreement (IEA/BA). Under this Agreement, Task IV deals specifically with biomass conversion topics. The cooperative activities consists of information exchange and coordination of national research programs on specific topics. The activities address biomass conversion in a systematic manner, dealing with the pretreatment of biomass prior to conversion, the subsequent conversion of the biomass to intermediate fuels or end-product energy, and then the environmental aspects of the conversion process. This document provides an outline of cooperative work to be performed in 1988. 1 fig., 2 …
Date: December 1, 1987
Creator: Stevens, D.J.
Object Type: Report
System: The UNT Digital Library
Bose-Einstein correlations in e/sup +/e/sup -/ collisions (open access)

Bose-Einstein correlations in e/sup +/e/sup -/ collisions

The MARK II detector is used to study the Bose-Einstein correlation between pairs and triplets of charged pions produced in hadronic decays of the J)psi), the ..sqrt..s = 4 to 7 GeV continuum above the J)psi), two photon events at ..sqrt..s = 29 GeV, and e/sup )plus/)e/sup )minus/) annihilation events at ..sqrt..s = 29 GeV as a function of Q/sup 2/, the four-momentum transfer squared. After corrections for Coulomb effects and pion misidentification, we find a nearly full Bose-Einstein enhancement ..cap alpha.. in the J)psi) and the two photon data and about half the maximum value in the other two data sets. The radius parameter )tau)(an average over space and time) given by pion pair analyses lies within a band of +-0.10 fm around 0.73 fm and is the same, within errors, for all four data sets. Pion triplet analyses also give a consistent radius of approx. 0.54 fm. fits to two-dimensional distributions R(q/sub T//sup 2/, q/sub C//sup 2/) of invariant components of Q/sup 2/ = q/sub T//sup 2/ )plus) q/sub C//sup 2/ give )tau)/sub T/ approx. )tau)C approx. )tau), where q/sub T/ is the transverse three-momentum difference calculated with respect to the net pair three-momentum, and q/sub C/ is …
Date: December 1, 1987
Creator: Juricic, I.
Object Type: Report
System: The UNT Digital Library
CDF (Collider Detector at Fermilab) detector simulation (open access)

CDF (Collider Detector at Fermilab) detector simulation

The Collider Detector at Fermilab (CDF) uses several different simulation programs, each tuned for specific applications. The programs rely heavily on the extensive test beam data that CDF has accumulated. Sophisticated shower parameterizations are used, yielding enormous gains in speed over full cascade programs. 3 refs., 5 figs.
Date: December 1, 1987
Creator: Freeman, J.
Object Type: Article
System: The UNT Digital Library
Cerium oxide coated anodes for aluminum electrowinning: Topical report, October 1, 1986-June 30, 1987 (open access)

Cerium oxide coated anodes for aluminum electrowinning: Topical report, October 1, 1986-June 30, 1987

Because of the cost of building and maintaining a carbon anode plant and the energy penalties associated with the use of carbon anodes in the production of aluminum, the use of inert anodes has long been proposed. Various cermet anodes have been investigated. In this paper, tests on a material, cerium oxyfluoride (CEROX), deposited in situ as an anode, are reported. (JDH)
Date: December 1, 1987
Creator: Walker, J. K.
Object Type: Report
System: The UNT Digital Library
Cermet-fueled reactors for advanced space applications (open access)

Cermet-fueled reactors for advanced space applications

Cermet-fueled nuclear reactors are attractive candidates for high-performance advanced space power systems. The cermet consists of a hexagonal matrix of a refractory metal and a ceramic fuel, with multiple tubular flow channels. The high performance characteristics of the fuel matrix come from its high strength at elevated temperatures and its high thermal conductivity. The cermet fuel concept evolved in the 1960s with the objective of developing a reactor design that could be used for a wide range of mobile power generating sytems, including both Brayton and Rankine power conversion cycles. High temperature thermal cycling tests for the cermet fuel were carried out by General Electric as part of the 710 Project (General Electric 1966), and by Argonne National Laboratory in the Direct Nuclear Rocket Program (1965). Development programs for cermet fuel are currently under way at Argonne National Laboratory and Pacific Northwest Laboratory. The high temperature qualification tests from the 1960s have provided a base for the incorporation of cermet fuel in advanced space applications. The status of the cermet fuel development activities and descriptions of the key features of the cermet-fueled reactor design are summarized in this paper.
Date: December 1, 1987
Creator: Cowan, C. L.; Palmer, R. S.; Taylor, I. N.; Vaidyanathan, S.; Bhattacharyya, S. K. & Barner, J. O.
Object Type: Article
System: The UNT Digital Library
Characteristics of spent fuel, high-level waste, and other radioactive wastes which may require long-term isolation: Appendix 2A, Physical descriptions of LWR (Light-Water Reactor) fuel assemblies (open access)

Characteristics of spent fuel, high-level waste, and other radioactive wastes which may require long-term isolation: Appendix 2A, Physical descriptions of LWR (Light-Water Reactor) fuel assemblies

This appendix includes a four-page Physical Description report for each assembly type identified from the current data. Where available, a drawing of an assembly follows the appropriate Physical Description report. If no drawing is available for an assembly, a cross-reference to a similar assembly is provided if possible. For Advanced Nuclear Fuels, Babcock and Wilcox, Combustion Engineering, and Westinghouse assemblies, information was obtained via subcontracts with these fuel vendors. Data for some assembly types are not available. For such assemblies, the information shown in this report was obtained from the open literature and by inference from reload fuels made by other vendors. Efforts to obtain additional information are continuing. Individual Physical Description reports can be generated interactively through the menu-driven LWR Assemblies Data Base system. These reports can be viewed on the screen or directed to a printer. Special reports and compilations of specific data items can be produced on request.
Date: December 1, 1987
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Characterization Investigation Study: Volume 3, Radiological survey of surface soils (open access)

Characterization Investigation Study: Volume 3, Radiological survey of surface soils

The Feed Materials Production Center was constructed to produce high purity uranium metal for use at various Department of Energy facilities. The waste products from these operations include general uncontaminated scrap and refuse, contaminated and uncontaminated metal scrap, waste oils, low-level radioactive waste, co-contaminated wastes, mixed waste, toxic waste, sludges from water treatment, and fly ash from the steam plant. This material is estimated to total more than 350,000 cubic meters. Other wastes stored in this area include laboratory chemicals and other combustible materials in the burn pit; fine waste stream sediments in the clear well; fly ash and waste oils in the two fly ash areas; lime-alum sludges and boiler plant blowdown in the lime sludge ponds; and nonradioactive sanitary waste, construction rubble, and asbestos in the sanitary landfill. A systematic survey of the surface soils throughout the Waste Storage Area, associated on-site drainages, and the fly ash piles was conducted using a Field Instrument for Detecting Low-Energy Radiation (FIDLER). Uranium is the most prevalent radioactive element in surface soil; U-238 is the principal radionuclide, ranging from 2.2 to 1790 pCi/g in the general Waste Storage Area. The maximum values for the next highest activity concentrations in the same …
Date: December 1, 1987
Creator: Solow, A.J. & Phoenix, D.R.
Object Type: Report
System: The UNT Digital Library
Characterization of solids in the Three Mile Island Unit 2 reactor defueling water (open access)

Characterization of solids in the Three Mile Island Unit 2 reactor defueling water

Because of the impact of poor water clarity on defueling operations at the Three Mile Island Unit 2 Nuclear Power Station, a study was undertaken to characterize suspended particulates in the reactor defueling water. The examination included cascade filtration through Nuclepore filters of progressively smaller pore sizes, using three water samples obtained at different times and after varying degrees of clarification. The solids collected on the filters were examined with a scanning electron microscope and analyzed with energy-dispersive x-ray fluorescence. A wide variety of solids was observed, and 26 elements were detected. These included all the materials expected from the reactor system (uranium, zirconium, silver, cadmium, indium, iron, chromium, and nickel), chemicals and zeolites used to decontaminate the water (aluminum, silicon, sodium), common impurities (potassium, chlorine, sulfur, magnesium, calcium, and others), as well as some unexpected metals (molybdenum, manganese, bromine, and lead). There was also evidence for the presence of organic material. A diverse assortment of particles with widely varying surface properties was found to be present.
Date: December 1, 1987
Creator: Campbell, D. O.
Object Type: Report
System: The UNT Digital Library
Chickasha Daily Express (Chickasha, Okla.), Vol. 96, No. 287, Ed. 1 Tuesday, December 1, 1987 (open access)

Chickasha Daily Express (Chickasha, Okla.), Vol. 96, No. 287, Ed. 1 Tuesday, December 1, 1987

Daily newspaper from Chickasha, Oklahoma that includes local, state, and national news along with advertising.
Date: December 1, 1987
Creator: Drew, Charles C.
Object Type: Newspaper
System: The Gateway to Oklahoma History
The Christian Chronicle (Oklahoma City, Okla.), Vol. 44, No. 12, Ed. 1 Tuesday, December 1, 1987 (open access)

The Christian Chronicle (Oklahoma City, Okla.), Vol. 44, No. 12, Ed. 1 Tuesday, December 1, 1987

Monthly newspaper from Oklahoma City, Oklahoma that includes news and information about the Churches of Christ along with advertising.
Date: December 1, 1987
Creator: Norton, Howard W. & McMillion, Joy L.
Object Type: Newspaper
System: The Portal to Texas History
Comprehensive data base of high-level nuclear waste glasses: September 1987 status report: Volume 1, Discussion and glass durability data (open access)

Comprehensive data base of high-level nuclear waste glasses: September 1987 status report: Volume 1, Discussion and glass durability data

The Materials Characterization Center (MCC) at Pacific Northwest Laboratory is assembling a comprehensive data base (CDB) of experimental data collected for high-level nuclear waste package components. Data collected throughout the world are included in the data base; current emphasis is on waste glasses and their properties. The goal is to provide a data base of properties and compositions and an analysis of dominant property trends as a function of composition. This data base is a resource that nuclear waste producers, disposers, and regulators can use to compare properties of a particular high-level nuclear waste glass product with the properties of other glasses of similar compositions. Researchers may use the data base to guide experimental tests to fill gaps in the available knowledge or to refine empirical models. The data are incorporated into a computerized data base that will allow the data to be extracted based on, for example, glass composition or test duration. 3 figs.
Date: December 1, 1987
Creator: Kindle, C. H. & Kreiter, M. R.
Object Type: Report
System: The UNT Digital Library
Comprehensive data base of high-level nuclear waste glasses: September 1987 status report: Volume 2, Additional appendices (open access)

Comprehensive data base of high-level nuclear waste glasses: September 1987 status report: Volume 2, Additional appendices

The Materials Characterization Center (MCC) is assembling a comprehensive data base (CDB) of experimental data collected for high-level nuclear waste package components. The status of the CDB is summarized in Volume I of this report. Volume II contains appendices that present data from the data base and an evaluation of glass durability models applied to the data base.
Date: December 1, 1987
Creator: Kindle, C. H. & Kreiter, M. R.
Object Type: Report
System: The UNT Digital Library
The coordination cluster theory for metallic solutions (open access)

The coordination cluster theory for metallic solutions

The coordination cluster theory for the thermodynamic properties of a dilute solute in a binary or higher order solvent. Although the CCT has been applied to liquids, it can be modified for solids. The theory permits one to describe the thermodynamic properties of a solute in a binary solvent in terms of the solute properties in the pure solvent components, the properties of the binary mixture and one unknown parameter. In principle, the properties of solutes in multicomponent solvents can be calculated from those in the subsidiary binary solvents. Modern quantum mechanical methods for the calculation of the energetics of metal solutions could be used to place the theory on a firm fundamental basis by testing the approximations in the theory and determining the unknown parameters. 9 refs., 3 figs.
Date: December 1, 1987
Creator: Blander, M. & Saboungi, M.L.
Object Type: Article
System: The UNT Digital Library