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Research in theoretical physics. Progress report, September 1, 1976--March 31, 1977. [Summaries of research activities at John's Hopkins University]
Gauge theories on coset spaces and dynamical mechanisms for generating internal symmetries were investigated. Gauge theories on cosets with respect to maximal subgroups of local internal symmetry groups contain reduced number of dynamically independent gauge fields. The transformation law of the gauge fields is nonlinear. Such theories can be interpreted in terms of a spontaneously broken internal symmetry. Internal symmetries may be generated in multidimensional geometric theory with vacuum solutions of the cylindrical type. Spinor fields on such spaces support intrinsically broken, approximate internal symmetries.
Date:
February 1, 1977
Creator:
Domokos, G.
System:
The UNT Digital Library
Interaction of an iridium-clad RTG heat source unit with a simulated terrestrial environment. [/sup 238/PuO/sub 2/]
An iridium-clad, 100-W /sup 238/PuO/sub 2/ sphere, a prototype for the multihundred-watt radioisotope thermoelectric generator, was exposed for 1 y to a simulated temperate humid climate in an environmental test chamber containing sandy soil. The hot sphere sank into the soil after the first rain, then gradually acquired a hard crust around it as a result of the rainwater reacting with the hot soil during successive rains. Time and temperature profiles of the sphere were recorded during the weekly rains, and the air and rainwater that percolated through the soil were monitored for plutonium. No plutonium was released from the sphere. Aside from the crust formation, very little reaction occurred between the hot iridium shell and the soil.
Date:
February 1, 1976
Creator:
Patterson, J. H.; Herrera, B.; Nelson, G. B.; Matlack, G. M. & Waterbury, G. R.
System:
The UNT Digital Library
Atlantic Richfield Hanford Company: process technology and process development. Quarterly report, October 1976--December 1976
None
Date:
February 1, 1977
Creator:
unknown
System:
The UNT Digital Library
Results of the radiological survey at Diebold Safe Company, 1550 Grand Boulevard, Hamilton, Ohio (HO001)
At the request of the US Department of Energy (DOE), a group from Oak Ridge National Laboratory conducted investigative radiological surveys at Diebold Safe Company, 1550 Grand Boulevard, Hamilton, Ohio in 1988 and 1989. The purpose of the surveys was to determine whether the property was contaminated with radioactive residues, principally {sup 238}U. The surveys included gamma scans; direct and transferable measurements of alpha, beta, and gamma radiation levels; and dust, debris, air, and soil sampling for radionuclide analyses. 6 refs., 6 figs., 5 tabs.
Date:
February 1, 1990
Creator:
Foley, R. D. & Floyd, L. M.
System:
The UNT Digital Library
The ultimate structure of matter: The high energy physics program from the 1950s through the 1980s
This discusses the following topics in High Energy Physics: The Particle Zoo; The Strong and the Weak; The Particle Explosion; Deep Inside the Nucleon; The Search for Unity; Physics in Collision; The Standard Model; Particles and the Cosmos; and Practical Benefits.
Date:
February 1, 1990
Creator:
unknown
System:
The UNT Digital Library
Structure of glasses containing transition metal ions. Progress report, June 1, 1975--January 31, 1976. [Lead silicate and alkaline earth nitrate host glasses]
Summarized is work on the structure of transition metal ion-containing silicate, borate, and other insulator glasses. Raman spectra were measured on lead silicate and on alkali-alkaline earth nitrate glasses. Raman spectra of lead silicate glasses are strongly polarized. The high frequency modes are greatly broadened with respect to alkali silicate glasses and new features appear in the low frequency region related to the lead concentration. The nitrate glass Raman spectra show broadened bands in more or less the positions expected from the molecular modes of the nitrate ions. The broadening and some splitting of these bands can be interpreted in terms of a distribution of local fields around the nitrate ions. An extensive series of chromium-containing silicate and borate glasses were prepared. Chromium appears in both Cr/sup 3 +/ and Cr/sup 6 +/ states. The Raman spectra show that hexavalent chromium exists in the glasses as molecular chromate or dichromate-like clusters. Cr/sup 6 +/ is not incorporated into the network. The local environment of Cr/sup 3 +/ was investigated by optical absorption and luminescence spectroscopy. The optical properties of Cr/sup 3 +/ in silicates were largely independent of base glass composition, which is not true of the borates. A study …
Date:
February 1, 1976
Creator:
Brawer, S. A. & White, W. B.
System:
The UNT Digital Library
Survey and analysis of small business and minority business enterprise participation in solar energy procurement activity
The findings of a survey of Small Business and Minority Business Enterprise participation in Solar Energy Programs as a result of procurement actions by the Energy Research and Development Administration, Division of Solar Energy, and subcontract actions by Solar Energy prime contractors for Fiscal Year 1976 and the Transition Quarter (FY76 and TQ) are presented. Also, information about awards made to Small Business/Minority Business Enterprise (SB/MBE) by other Federal Agencies during the same period is provided. The primary findings of this survey indicate that $6.7 million of a total $94.3 million Solar Energy outlay, for FY76 and the TQ, was allocated to Small Business in the form of prime contracts. Another $16.6 million was subcontracted to Small business/minority business enterprise (SB/MBE) by Solar Energy Prime contractors during this period. This represents a total of $23.3 million Solar Energy dollars contracted and subcontracted to SB/MBE's or 24.7 percent of the $94.3 million Solar Energy outlay during FY76 and the TQ. (WHK)
Date:
February 1, 1977
Creator:
unknown
System:
The UNT Digital Library
Gamma heating in LMFBR media
State-of-the-art approaches for the calculation of gamma heating in LMFBR core, blanket and reflector regions have been evaluated, with particular emphasis on coupled neutron-gamma methods/cross section sets. The major source of calculational error was found to be the apparent failure to impose a mass-energy balance on total gamma energy yield from neutron capture and other interactions in the preparation of representative neutron-gamma cross section sets. The applicability of many simplifying assumptions was demonstrated, including: volume-weighted homogenization, insensitivity to the shape of the gamma-source-spectrum, gamma energy deposition equal to gamma energy source more than 10 cm inside large zones of uniform composition, and the negligible effect of bremsstrahlung. A simple one-group method was developed to permit rapid, accurate estimation of the large (factor of 2) changes in the gamma energy deposition-to-source ratio possible near region interfaces. The approach, which also ensures conservation of mass-energy, was used in conjunction with coupled neutron-gamma computations to verify that previous experimental measurements of gamma heating in an LMFBR blanket mockup at M. I. T. were in accord with theoretical expectations within the experimental precision of +-10%.
Date:
February 1, 1976
Creator:
Kalra, M. S. & Drisoll, M. J.
System:
The UNT Digital Library
Thermal expansion of /sup 238/PuO/sub 2/
The linear thermal expansion of stoichiometric /sup 238/PuO/sub 2/ was measured over the range 25 to 1600/sup 0/. The value of ..delta..L/L/sub 0/ per degree C, calculated from the data, is ..delta..L/L/sub 0/ = -2.249 x 10/sup -4/ + 9.020 x 10/sup -6/T - 1.130 x 10/sup -9/T/sup 2/ + 1.525 x 10/sup -12/T/sup 3/.
Date:
February 1, 1976
Creator:
Andrew, J. F.; Zocher, R. W. & Kent, R. A.
System:
The UNT Digital Library
User's manual for the Oak Ridge Tokamak Transport Code
A one-dimensional tokamak transport code is described which simulates a plasma discharge using a fluid model which includes power balances for electrons and ions, conservation of mass, and Maxwell's equations. The modular structure of the code allows a user to add models of various physical processes which can modify the discharge behavior. Such physical processes treated in the version of the code described here include effects of plasma transport, neutral gas transport, impurity diffusion, and neutral beam injection. Each process can be modeled by a parameterized analytic formula or at least one detailed numerical calculation. The program logic of each module is presented, followed by detailed descriptions of each subroutine used by the module. The physics underlying the models is only briefly summarized. The transport code was written in IBM FORTRAN-IV and implemented on IBM 360/370 series computers at the Oak Ridge National Laboratory and on the CDC 7600 computers of the Magnetic Fusion Energy (MFE) Computing Center of the Lawrence Livermore Laboratory. A listing of the current reference version is provided on accompanying microfiche.
Date:
February 1, 1977
Creator:
Munro, J. K.; Hogan, J. T.; Howe, H. C. & Arnurius, D. E.
System:
The UNT Digital Library
Consensus forecast of U. S. electricity supply and demand to the year 2000
Recent forecasts of total electricity generating capacity and energy demand as well as for electricity produced from nuclear energy and hydroelectric power are presented in tables and graphs to the year 2000. A forecast of the distribution of type of fuel and energy source that will supply the future electricity demand is presented. Use of electricity by each major consuming sector is presented for 1975. Projected demands for electricity in the years 1985 and 2000, as allocated to consuming sectors, are derived and presented.
Date:
February 1, 1976
Creator:
Lane, J. A.
System:
The UNT Digital Library
Tests of 5-inch Venetian-blind-type photomultiplier tubes. [For lead glass Cherenkov counters]
Test results are described on three inexpensive 5-inch photomultiplier tubes of Venetian-blind construction to be used for collection of Cherenkov light produced by electromagnetic showers in lead glass. Parameters evaluated include photoelectron collection efficiency, pulse-height resolution, amplitude and rate stability, and linearity.
Date:
February 1, 1977
Creator:
Gilad, S.; Baer, H. W.; Cooper, M. D. & Moinester, M. A.
System:
The UNT Digital Library
Coal Technology Program. Progress report for December 1975
This report, the seventeenth of a series, is a compendium of monthly progress reports in support of the increased utilization of coal as a source of clean energy. The projects reported include those for hydrocarbonization, solid-liquid separations, chemical research and development, engineering evaluations of nuclear process heat for coal conversion, engineering evaluations of the hydrocarbonization and synthoil processes, and coal-fueled MIUS. Two more runs were completed with the bench-scale hydrocarbonization research system using nitrogen at 20 atm with the preheater at 1400/sup 0/F and the reactor at 1250/sup 0/F. Some difficulty was encountered with the coal feeder and corrective modifications are underway. Revisions and additions were made to the flowsheet for a plant using direct steam gasification of coal, which is thermally driven by a 3000-MW(t) VHTR. In the engineering evaluations work for the synthoil process, flow diagrams for four units were finalized. A preliminary facility site plan was developed. Conceptual design of the solids-liquid separation plant specifying centrifugation followed by filtration of the thickened underflow was completed. In the MIUS program, a /sup 1///sub 12/ scale model of the latest layout is being constructed. (auth)
Date:
February 1, 1976
Creator:
unknown
System:
The UNT Digital Library
Evaluation of Millstone Nuclear Power Plant, Environmental Impact prediction, based on monitoring programs
This report evaluates the nonradiological monitoring program at Millstone Nuclear Power Plant. Both operational as well as preoperational monitoring programs were analyzed to produce long-term (5 yr or longer) data sets, where possible. In order to determine the effectiveness of these monitoring programs, the appropriate data sets have to be analyzed by the appropriate statistical analysis. Thus, both open literature and current statistical analysis being developed at Pacific Northwest Laboratories (PNL) were employed in data analysis.
Date:
February 1, 1977
Creator:
Gore, K. L.; Thomas, J. M.; Kannberg, L. D. & Watson, D. G.
System:
The UNT Digital Library
Hazards control progress report No. 51, July--December 1975
Progress is reported on research projects in the fields of radiation protection, industrial hygiene, instrument development, fire safety, decontamination, and environmental protection. (HLW)
Date:
February 16, 1976
Creator:
Crites, T. R. (comp.)
System:
The UNT Digital Library
Summary of calculations of dynamic response characteristics and design stress of the 1/5 scale PSE torus. [BWR; MK1 pressure suppression system]
The Lawrence Livermore Laboratory is currently involved in a 1/5 scale testing program on the Mark I BWR pressure suppression system. A key element of the test setup is a pressure vessel that is a 90/sup 0/ sector of a torus. Proper performance of the 90/sup 0/ torus depends on its structural integrity and structural dynamic characteristics. It must sustain the internal pressurization of the planned tests, and its dynamic response to the transient test loads should be minimal. If the structural vibrations are too great, interpretation of important load cell and pressure transducer data will be difficult. The purpose of the report is to bring together under one cover calculations pertaining to the structural dynamic characteristics and structural integrity of 90/sup 0/ torus. The report is divided into the following sections: (1) system description in which the torus and associated hardware are briefly described; (2) structural dynamics in which calculations of natural frequency and dynamic response are presented; and (3) structural integrity in which stress calculations for design purposes are presented; and an appendix which contains an LLL internal report comparing the expected load cell response for a three and four-point supported torus.
Date:
February 9, 1977
Creator:
Arthur, D.
System:
The UNT Digital Library
Fission product beta and gamma energy release. Quarterly progress report for October--December 1975
Preliminary experimental information for beta-ray energy release from fission product decay following thermal-neutron fission of /sup 235/U has been obtained for cooling times between 3 and 14,400 secs. The data were obtained as pulse-height spectra for beta energies between 0.25 and 8 MeV using a two-crystal scintillation spectrometer, and were unfolded to give beta-ray energy spectra of moderate resolution. Two irradiation times, t/sub i/ = 2.4 and 100 sec, were studied. The energy release data were studied. The energy release data were obtained by integrating the observed spectra and then estimating the contribution for E/sub ..beta../ less than 0.25 MeV. Difficulties encountered in this first experiment using the beta-ray detection equipment are discussed. Previously reported preliminary gamma-ray spectra have been compared with spectra calculated using spectral information in the ENDF/B--IV data file for approximately 180 fission products. Several comparisons are presented for t/sub i/ = 100 secs. As expected the comparison is not very good for short cooling times, but is encouraging for t/sub cool/ approximately 2000 secs.
Date:
February 1, 1976
Creator:
Dickens, J. K.; Love, T. A.; McConnell, J. W.; Emery, J. F. & Peelle, R. W.
System:
The UNT Digital Library
Theoretical calculation of Raman scattering cross sections for use in flame analysis
The laser Raman scattering analysis of combustion flames requires a knowledge of the scattering cross sections for a variety of molecular species. Since cross sections are known for only the most common and most stable of molecules (e.g., N/sub 2/, O/sub 2/ and H/sub 2/), a program to calculate cross sections for other molecules of interest to combustion analysis has been initiated. In this paper theoretically-determined cross sections for H/sub 2/, N/sub 2/, OH, LiH, and O/sub 2/ are presented. Comparison with the few experimentally determined cross sections indicates that the theoretical approach is a reliable method for determining Raman scattering cross sections for those molecules whose cross sections cannot be readily determined experimentally. (auth)
Date:
February 1, 1976
Creator:
Coll, C. F. & Melius, C. F.
System:
The UNT Digital Library
DT fusion neutron irradiation of ANL electron microscopy samples, LLL ''tritium-tricked'' niobium, LLL Al/sub 2/O/sub 3/, SiC, and B/sub 4/C, and an LLL sputtering experiment
The experimental procedure for irradiating the above specimens is given. No results are presented. (MOW)
Date:
February 25, 1976
Creator:
MacLean, S. C.
System:
The UNT Digital Library
Properties of carbonized and converted uranium-loaded weak-acid resins
Weak-acid ion-exchange resins have been found to provide a practical method for fabricating uranium-containing HTGR fuel kernels. Two steps, thermal decomposition or carbonization and carbothermic reduction of UO/sub 2/ or conversion, are required in the manufacture of these kernels. The property variations during carbonization of uranium-loaded weak-acid resin-derived fuel proceeds in a manner closely analogous to its thermogravimetric characteristics, particularly the weight loss, volume loss, carbon-to-uranium ratio, density, and particle size. The heating rate through the critical portion of the thermogravimetric curve closely controls the resultant weight loss, volume loss, density, carbon-to-uranium ratio, and subsequent thermal behavior. The optimum carbonization cycle derived dictates a heating rate of 2/sup 0/C/min from 350 to 440/sup 0/C, and the maximum practicable rate outside of this range. The conversion of the carbonized material is predictable from classical bulk thermodynamics for removal of carbon monoxide from UO/sub 2/ + C. Relative phase compositions of UO/sub 2/, UC/sub 2/ and UC/sub 1-x/O/sub x/ can be controlled by adjusting conversion conditions. Agglomeration during conversion can be controlled by lowering the carbonization rate and/or conversion temperature and increasing gas flow. During this process Duolite C-464 resin appears more resistant to sticking than does Amberlite IRC-72.
Date:
February 1, 1977
Creator:
Weber, G. W.; Beatty, R. L. & Tennery, V. J.
System:
The UNT Digital Library
Pacific Northwest Laboratory annual report for 1975 to the ERDA Division of Biomedical and Environmental Research. Part 4. Physical and analytical sciences and analysis and assessment
Separate abstracts were prepared for 16 sections of this report. A list is included of 21 publications during the time period covered. (CH)
Date:
February 1, 1976
Creator:
Nielsen, J. M.
System:
The UNT Digital Library
Cross-flow filtration in physical-chemical treatment of municipal sewage effluents
In separations of solids from liquids by filtration, the motion of liquid is customarily normal to the filtering surface, and solids are left on the filter. In a variation called cross-flow filtration, liquid is pumped parallel to the filtering surface. By this device, thickening of flux-limiting filtercake is slowed, and the original stream is separated into a large volume of filtrate and a concentrated slurry of solids. Results reported here were obtained in cross-flow filtration used as an element in physical-chemical treatment of municipal sewage, mostly with the effluent from primary settling, but in some cases, with clarified activated sludge effluent as feed. Filtrate from passage through fabric tubes (1-inch fire-hose jackets) of primary effluent, treated with iron or aluminum salts, with powdered activated carbon (PAC), or with both hydrolyzable ions and PAC, was generally of quality superior in turbidity, organic carbon and other respects to the effluent from biological secondary treatment. Effects on product quality and flux of pressure, circulation velocity, additive concentration, water recovery, pH and other variables were investigated. Based on production rates obtained, estimates of treatment costs were made.
Date:
February 1, 1976
Creator:
Mahlman, H. A.; Sisson, W. G.; Kraus, K. A. & Johnson, J. S. Jr.
System:
The UNT Digital Library
Data input manual for RSI/TEVCO: a thermo/viscoelastic finite element computer program
RSI/TEVCO is a plane finite element code designed to analyze elastic, thermoelastic, viscoelastic, or thermoviscoelastic problems. The basic element is the eight noded isoparametric quadrilateral element, but a six noded subparametric triangular element may be used separately or for gradation purposes with quadrilateral elements.
Date:
February 1, 1977
Creator:
Callahan, G. D. & Fossum, A. F.
System:
The UNT Digital Library
Development of the prototype Munitions Case Moisture Meter, Model ORNL-1
There is a great need for a rapid and simple means of determining the moisture content in combustible cartridge case (ccc) munitions. Previous studies have demonstrated that accumulation of moisture in ccc rounds, such as the M829, leads to softening of the case wall and weakening of the adhesive joint. Moisture in the ccc can lead to incomplete combustion of the case upon firing the round. Currently, there are no facile methods for measuring the moisture content. A prototype portable meter for non-destructive and rapid estimation of moisture in ccc has been developed. The Munitions Case Moisture Meter Model ORNL-1 demonstrates the feasibility of developing an instrument based on the moisture dependence of dielectric properties, to measure moisture in ccc munitions in storage and in the field. These instruments are simple, inexpensive, lightweight, portable, low-power battery operated, and intrinsically safe. They provide nondestructive, noninvasive, and rapid measurements. Calibration data for the prototype are not available at this time. Therefore, calibration of the meter and the development of a scale reading directly moisture content in munitions rounds could not be completed. These data will be supplied by the US Army from its tests of the meter with actual munitions. However, experimental …
Date:
February 24, 1993
Creator:
Agouridis, D. C.; Gayle, T. M. & Griest, W. H.
System:
The UNT Digital Library