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Structural analysis of the West Hackbery No. 6 SPR storage cavern

Description: Four separate structural analyses of the West Hackberry No. 6 SPR storage cavern are presented. One analysis covers the creep response of the cavern beginning shortly before the time when an accidental fire occurred and proceeding through the cavern recertification pressure test. The second analysis models the surface uplife that is expected during the same pressure test. The third and fourth numerical studies investigate the structural response of West Hackberry No. 6 to slabbing and a rapid pressure drop. All analyses indicate that this cavern should be structurally stable for the conditions assumed.
Date: August 1, 1980
Creator: Benzley, S.E.
Partner: UNT Libraries Government Documents Department
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Numerical study of the NOL large-scale gap test

Description: The NOL large-scale gap test has been modeled numerically using the LASL reactive hydrodynamics code 2DE with Forest Fire burn rates. The model gives good agreement between calculated and experimental critical gap values for VTQ-2 and Composition B. The calibration of peak pressure in the gap versus gap length has been obtained from these calculations, and is in good agreement with the published experimental curve. The two-dimensional nature of the gap test is evident from the curvature of the shock wave in the gap and test sample, and from the observed distance of run to detonation in the test samples.
Date: January 1, 1980
Creator: Bowman, A.L.
Partner: UNT Libraries Government Documents Department
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Compilation of cores and cuttings from U. S. Government-sponsored geothermal wells

Description: This compendium lists the repositories holding geothermal core and well cuttings from US government-sponsored geothermal wells. Also, a partial listing of cores and cutting from these wells is tabulated, along with referenced reports and location maps. These samples are available to the public for research investigations and studies, usually following submission of an appropriate request for use of the samples. The purpose of this compilation is to serve as a possible source of cores and cuttings that might aid in enhancing rock property studies in support of geothermal log interpretation.
Date: July 1, 1980
Creator: Mathews, M.; Gambill, D.T. & Rowley, J.C.
Partner: UNT Libraries Government Documents Department
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Interactions of tailings leachate with local liner materials found at Canonsburg, Pennsylvania.

Description: The mill tailings site at Canonsburg, Pennsylvania is the first mill site to receive remedial action under the Department of Energy's Uranium Mill Tailings Remedial Action Program. Part of this remedial action will require excavating the 53,500 m/sup 3/ (70,000 yd/sup 3/) of tailings on the site having a specific activity exceeding 100 pCi/g, and encapsulating these contaminated tailings in a clay-lined cell. As part of the remedial action effort, Pacific Northwest Laboratory has been studying the interactions of tailings and tailings leachate with locally occurring clays proposed for liner materials. These studies include physical and chemical characterization of amended and unamended local clays, chemical characterization of the tailings, column studies of tailings leached with deionized water, and column studies of clays contacted with tailings solutions to determine the attenuation properties of the proposed liner materials. Column studies of tailings leached with deionized water indicated that the Canonsburg tailings could represent a source of soluble radium-226 and uranium-238, several trace metals, cations, and the anions SO/sub 4/, NO/sub 3/, and Cl. Of these soluble contaminants, uranium-238, radium-226, the trace metals As and Mo, and the anions F and SO/sub 4/ were present at levels exceeding maximum concentration levels in the tailings leaching column effluents. However, local clays, both in amended and unamended form were effective in attenuating contaminant migration. The soil amendments tested failed to increase radium attenuation. The tailings leaching studies indicated that the tailings will produce leachates of neutral pH and relatively low contaminant levels for at least 200 years. We believe that compacting the tailings within the encapsulation cell will help to reduce leaching of contaminants from the liner system, since very low permeabilities (<10/sup -8/ cm/s) were observed for even slightly compacted tailings materials.
Date: April 1, 1984
Creator: Dodson, M.E.; Gee, G.W. & Serne, R.J.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division Unit Operations Section Monthly Progress Report, September 1961

Description: Nine samples of ThO/sub 2/ -UO/sub 2/ prepared as part of the solgel process development studies showed no consistent effects from small variations in several process parameters. The reaction of methane and copper oxide was studied. Engineering studies of the continuous dissolution of simulated U-Zr-Sn fuels in 6.5 M NH4F, 0.6-1.0 M NH/sub 4/NO/sub 3/, 0.1 M H/sub 2/O/sub 2/ were continued in modified 6-in.-dia. equipment. A total of 1642 kg of U from NaK bonded SRE Core I fuel rods wad dejacketed to date/su Initial operability tests of the 250 ton prototype shear unit showed a number of minor modifications are warranted. Center tube temperatures measured in a vertical 64 tube electrically heated simulated fuel element bundle were very near those previously obtained in the horizontal position. A 304 SS tube containing eutectic NaK was dissolved by HF in fused saIt at a tube wall penetration rate of approximates 2 mils/hr. Partial differential equations were derived from the concentration of unreacted UF/sub 6/ as a function of time and position in a sphere of NaF during sorption of UF/sub 6/. Calcium nitrate solution was added directly to the pot calciner during Purex feeding to give smoother operation of the feeding system. (auth)
Date: April 1, 1962
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Partner: UNT Libraries Government Documents Department
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Search for the neutrinoless muon decay. mu. /sup +/. -->. e/sup +/. gamma

Description: Separate muon, electron, and tau numbers are conserved in the minimal standard model of electroweak interactions with massless neutrinos. However, in many extensions to the standard model, separate lepton numbers are not expected to be conserved quantities. A new search for muon number non-conserving processes has been undertaken at the Los Alamos Meson Physics Facility (LAMPF), specifically to look for three neutrinoless decay modes of the muon. The search for the decay of a muon to an electron and a photon is discussed here. A new detector facility, located in the LAMPF stopped muon channel, was developed for this experiment. This Crystal Box detector consists of a cylindrical drift chamber surrounded by a plastic scintillator hodoscope and a large solid angle, modularized, NaI(Tl) calorimeter. The apparatus measures the trajectories, relative timing, and energies of charged particles and photons from the decays of positive muons stopped in a central target. The assembly and calibration of the detector are described, and the procedure for taking data is discussed. The sample of 1.3 million candidate events, from the first data run of the Crystal Box, was analyzed using a maximum-likelihood method. The upper limit on the branching ratio, relative to normal muon decay, for a muon decaying to an electron and a photon is found to be consistent with previous measurements. With 90% confidence, the branching ratio for this neutrinoless decay is observed to be less than 2.8 x 10/sup 10/.
Date: July 1, 1985
Creator: Wilson, S.L.
Partner: UNT Libraries Government Documents Department
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Solar-thermal energy conversion and storage: cyclohexane dehydrogenation. Progress report, 30 September 1977-30 June 1978

Description: The objective of this project is to provide research support for the benzene/cyclohexane heat pipe development program at Sandia. The kinetics of the cyclohexane decomposition (energy collection) reaction over a commercially available naphtha reforming catalyst (RD-150, Englehard Industries) in the temperature range 400 to 800/sup 0/F and pressures of 1 to 40 atmospheres were measured. Significant amounts of side products such as toluene and butane were identified at temperatures above 550/sup 0/F at atmospheric pressure and significant mass transfer limitations on conversions were observed at the higher space velocities and higher temperatures. No significant decreases in catalyst activity were measured at temperatures below 800/sup 0/F. However, at 800/sup 0/F there was a significant decrease in catalyst activity which does not appear to be a poisoning problem but a thermal limitation on catalyst effectiveness. A test facility has been fabricated to study the behavior of the benzene/cyclohexane (or any other gas phase catalytic reaction) system and its catalysts under long term cycling at temperatures up to 1000/sup 0/F, and pressures up to 1000 psig at a wide variety of space velocities. A mathematical model was developed which simulates the dynamic behavior of the collector (endothermic) reactor and allows the evaluation of such things as startup, shutdown, switching and process control algorithms.
Date: July 1, 1978
Creator: Ritter, A.B.; DeLancey, G.B.; Schneider, J. & Silla, H.
Partner: UNT Libraries Government Documents Department
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Energy-Exchange Project

Description: The purpose of the study was to determine what energy savings can be achieved by coordinating the resources and requirements of two facilities, the 26th Ward Water Pollution Control Plant (WPCP) and a housing development named Starrett City with its own total energy system. It was determined that three energy exchange options were economically and technically feasible. These include: the transfer of digester gas produced at the 26th Ward to the boilers at the Starrett City's total energy plant (TEP); the transfer of hot water heated at the TEP to the 26th Ward for space and process heating; and the transfer of coal effluent waste water from the 26th Ward to the condenser cooling systems at the TEP. Technical information is presented to support the findings. The report addresses those tasks of the statement of work dedicated to data acquisition, analysis, and energy conservation strategies internal to the Starrett City TEP and the community it supplies as well as to the 26th Ward WPCP. (MCW)
Date: April 1, 1982
Partner: UNT Libraries Government Documents Department
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Geothermal resources in California: the problems and the potential

Description: The report is presented under the following section headings: introduction; conclusions and recommendations; legislative activity in 1973; United Nations Geothermal Conference; International Geothermal Conference--1975; National Conference on Geothermal Energy, May 10--11, Palm Springs, Calif.; Imperial Valley field trip and joint interim hearing October 16--17, 1973 (Senate Committee on Natural Resources and Wildlife on Senate Bill 577 in San Diego); hearing of the Subcommittee on Geothermal Resources and the Senate Committee on Public Utilities and Corporations, Nov. 12, 1973 in San Francisco (public access to steam at The Geysers); hearing of the Senate Committee on Natural Resources and Wildlife on the continued availability of natural gas and other sources of energy, Nov. 15, 1973, in Martinez, Calif; and Appendix. (JGB)
Date: January 1, 1973
Partner: UNT Libraries Government Documents Department
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Physical fitness training reference manual for security force personnel at fuel cycle facilities possessing formula quantities of special nuclear materials

Description: The recommendations contained throughout this NUREG are being provided to the Nuclear Regulatory Commission (NRC) as a reference manual which can be used by licensee management as they develop a program plan for the safe participation of guards, Tactical Response Team members (TRTs), and all other armed response personnel in physical fitness training and in physical performance standards testing. The information provided in this NUREG will help licensees to determine if guards, TRTs, and other armed response personnel can effectively perform their normal and emergency duties without undue hazard to themselves, to fellow employees, to the plant site, and to the general public. The recommendations in this NUREG are similar in part to those contained within the Department of Energy (DOE) Medical and Fitness Implementation Guide which was published in March 1991. The guidelines contained in this NUREG are not requirements, and compliance is not required. 25 refs.
Date: September 1, 1991
Creator: Arzino, P. A.; Caplan, C. S. & Goold, R. E. (California State Univ., Hayward, CA (United States). Foundation)
Partner: UNT Libraries Government Documents Department
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Peregrine Falcon study. Final report

Description: Three papers are included. A separate abstract was prepared for each. (MHR)
Date: February 1, 1980
Partner: UNT Libraries Government Documents Department
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State of the art of pressurized fluidized bed combustion systems

Description: This report was prepared at the request of the Tennessee Valley Authority (TVA) to clarify the development status of the pressurized fluidized bed combustor (PFBC) and to place in perspective the problems which are yet to be solved before commercialization of the concept is practical. This report, in essence, supersedes the interim report published in 1979, Assessment of the State of the Art of Pressurized Fluidized Bed Combustion Systems. A brief overview of the PFBC concept is included citing potential advantages and disadvantages relative to atmospheric fluidized bed combustion (AFBC) and conventional pulverized coal plants. A survey of existing and developing PFBC experimental facilities is presented in some detail which includes the major accomplishments at the respective facilities. Recent data on plant emissions, turbine/gas cleanup systems, and overall efficiency are provided. Findings of several design studies are also discussed. The results of recent gas turbine and cascade tests have been encouraging although the full assessment of the accomplishments have not been made. The delay in construction of the Grimethorpe plant causes further delay in proof-testing full-size, rotating turbomachinery. Several parameters are recommended for further assessment in design studies including: (1) effect of turbine life on cost of power; and (2) effect of reduced gas turbine inlet temperature and pressure on cost of power.
Date: September 1, 1980
Creator: Graves, R.L.
Partner: UNT Libraries Government Documents Department
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HRT CORROSION SAMPLES--ADDITIONAL DATA ON SPECIMENS REMOVED PRIOR TO RUN NO. 20

Description: Results of the examinations of corrosion specimens exposed in the HRT are presented. Specimens examined include core screen samples, core specimen array No. 1, blanket specimen array No. 2, core solution line specimen arrays No. 103 and 103A, and blanket solution line specimen array No. 203. These data include corrosion rates, computed from specimen weight-changes, and results of chemical analyses of scales removed from the specimens or specimen holders. A summary is included of the HRT operating schedule during exposure of the specimens and of the status of examinations for the specimens removed from the reactor prior to run 20. (auth)
Date: February 1, 1961
Creator: Baker, J.E.; Silverman, M.D.; Jenks, G.H. & Olsen, A.R.
Partner: UNT Libraries Government Documents Department
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Startup and Initial Testing of SM-1 Core II With Special Components

Description: The loading operation for SM-1 Core II is described. Results of startup physics measurements (Test A-300 (Series) and fission product iodine monitoring in the primary coolant are given. The SM-1 Core II initial loading progressed satisfactorily, fulfilling the predictions of the zero power experiment performed at the Alco Criticality Facility. The initial cold clean five rod bank position was 6.53 in.; the initial hot, no xenon, five rod bank position was 9.62 in.; the initial hot, equilibrium xenon, five rod bank position was 11.41 in.; and the initial hot, peak xenon, five rod bank position was 12.14 in. Rods A and B were 19.00 in. in all four measurements. Stuck rod measurements indicated that an adequate shutdown margin was available with 20% of the rods fully withdrawn. All rod calibrations indicated a distinct shift and broadening of the peaks when compared with similar Core I calibrations. The temperature coefficient for Core II was 3.5 cents/ deg F at 440 deg F. Equilibrium xenon was worth approximately - 00 while peak xenon was worth - 43, both relative to the hot, no xenon core condition. During the period June 2, 1961 through September 30, 1961, the reactor operated at a total of 935.68 deg Fdays which is equivalent to 1.34 MWYR of energy release and represents an average load factor of 44% typical of training periods. The estimated reactivity in the core at startup is .00. A core life of 12.2 MWYR is predicted for the original configuration of Core II. The results of gross fission product iodine monitoring showed that those levels were about one-third to one-half of those found at the end of Core I Operation. (auth)
Date: February 28, 1962
Creator: Moote, F. G. & Schrader, E. W.
Partner: UNT Libraries Government Documents Department
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Magnetic Properties of Insulators. Quarterly Report No. 2 Covering Period May 15, 1961 to August 15, 1961

Description: The electron paramagnetic resonance (EPR) of color centers in additively colored KCl crystals is measured to observe the effects of optical bleaching at room temperature. Earlier measurements on the F-center are confirmed and the susceptibility is measured at 78 and 300 deg K over five decades of power, including the very low power region. The width and the saturation properties of the individual multiplets are studied in detail and the technique of making E PR measurements on inhomogeneously broadened lines is discussed. A calculation is presented which shows that a slight departure from a Lorentzian multiplet shape can account for the saturation data. The bleached crystals show a resonance which has a width of 35 gauss and a different rate of saturation than the F- center. This resonance is associated with the B-band which appears in the optical absorption. (auth)
Date: August 30, 1961
Creator: Markham, J. J.
Partner: UNT Libraries Government Documents Department
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Murgatroyd-an Ibm 7090 Program for the Analysis of the Kinetics of the Msre

Description: The IBM 7090 program Murgatroyd is a revised and extended version of the IBM 704 program PET-I, which solves (by a fifth-order Runge-Kutta procedure) the coupled firstorder differential equations for power, delayed neutron concentration, and temperature in a one-region reactor as a function of time, given an input reactivity variation represented by a series of linear ramps. The basic extensions were those which were necessary to include the effects of the separate heat capacities and temperature coefficients of the fuel sait and graphite in the MSRE, and of heat transfer between the fuel and graphite. In addition, the input and output sections of the previous program were modified to facilitate the use of the program in extensive parameter studies, and a calculation of the pressure rise in the core was included. Typical running times are of the order of l2 milliseconds per time step; a calculation of a 30-second power history using a 10 millisecond time step requires about 36 seconds of machine time. (auth)
Date: April 1, 1962
Creator: Nestor, C. W. Jr.
Partner: UNT Libraries Government Documents Department
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A Novel Coal Feeder for Production of Low Sulfur Fuel

Description: During the past three months, the coal feeding system has been tested and currently undergoing evaluation at the University of Cincinnati. The system consists primarily of an auger feed tube which is used to both convey and provide desulfurization of a high sulfur coal feedstock. The coal is conveyed at temperatures ranging from 350 to 550{degrees}C and under normal atmospheric pressure. Under these mild processing conditions, the coal partially pyrolizes and emits sulfur in the form of hydrogen sulfide while maintaining a relatively high heating value in the char product. The evolved gases are evacuated from the reactor (the feed tube) to another absorbing bed where H{sub 2}S reacts with the sorbent, usually lime or limestone. The resultant sorbent utilization is substantially higher than the values found in current dry scrubbing system and the produced low-sulfur char may then be used in a conventional steam boiler.
Date: January 1, 1990
Creator: Khang, S. J. & Keener, T. C.
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF A PROCESS FOR SODIUM BONDING OF EBR-II FUEL AND BLANKET ELEMENTS

Description: Procedures for assembling EBR-II fuel elements with annular sodium bonds between the uranium rods and the stainless steel claddings are outlined. The results of several meltdown and uranium-settling experiments are given. Bonding experiments were performed: furnace bonding, submerged canning, ultrasonic bonding, centrifuging, pressure pulsing, and vibratory bonding. Vibratory bonding was chosen for the production of the first EBR-II core. (D.L.C.)
Date: July 1, 1961
Creator: Sowa, E.S. & Kimont, E.L.
Partner: UNT Libraries Government Documents Department
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NRC plan for cleanup operations at Three Mile Island Unit 2

Description: This NRC Plan, which defines NRC&#x27;s functional role in cleanup operations at Three Mile Island Unit 2 and outlines NRC&#x27;s regulatory responsibilities in fulfilling this role, is the first revision to the initial plan issued in July 1980 (NUREG-0698). Since 1980, a number of policy developments have occurred which will have an impact on the course of cleanup operations. This revision reflects these developments in the area of NRC&#x27;s review and approval process with regard to cleanup operations as well as NRC&#x27;s interface with the Department of Energy&#x27;s involvement in the cleanup and waste disposal. This revision is also intended to update the cleanup schedule by presenting the cleanup progress that has taken place and NRC&#x27;s role in ongoing and future cleanup activities.
Date: February 1, 1982
Creator: Lo, R. & Snyder, B.
Partner: UNT Libraries Government Documents Department
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Fuel performance annual report for 1989

Description: This annual report, the twelfth in a series, provides a brief description of fuel performance during 1989 in commercial nuclear power plants and an indication of trends. Brief summaries of fuel design changes, fuel surveillance programs, fuel operating experience, fuel problems, high-burnup fuel experience, and items of general significance are provided. References to more detailed information and related US Nuclear Regulatory Commission evaluations are included.
Date: June 1, 1992
Creator: Bailey, W.J.; Berting, F.M. (Pacific Northwest Lab., Richland, WA (United States)) & Wu, S. (Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology)
Partner: UNT Libraries Government Documents Department
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