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Conceptual designs for modular OTEC SKSS. Final report
This volume presents the results of the first phase of the Station Keeping Subsystem (SKSS) design study for 40 MW/sub e/ capacity Modular Experiment OTEC Platforms. The objectives of the study were: (1) establishment of basic design requirements; (2) verification of technical feasibility of SKSS designs; (3) identification of merits and demerits; (4) estimates of sizes for major components; (5) estimates of life cycle costs; (6) deployment scenarios and time/cost/risk assessments; (7) maintenance/repair and replacement scenarios; (8) identifications of interface with other OTEC subsystems; (9) recommendations for and major problems in preliminary design; and (10) applicability of concepts to commercial plant SKSS designs. A brief site suitability study was performed with the objective of determining the best possible location at the Punta Tuna (Puerto Rico) site from the standpoint of anchoring. This involved studying the vicinity of the initial location in relation to the prevailing bottom slopes and distances from shore. All subsequent studies were performed for the final selected site. The two baseline OTEC platforms were the APL BARGE and the G and C SPAR. The results of the study are presented in detail. The overall objective of developing two conceptual designs for each of the two baseline OTEC …
Date:
February 29, 1980
Creator:
unknown
System:
The UNT Digital Library
Technical evaluation report on the monitoring of electric power to the reactor-protection system for the Pilgrim Nuclear Power Station
This report documents the technical evaluation of the monitoring of electric power to the reactor protection system (RPS) at the Pilgrim Nuclear Power Station. The evaluation is to determine if the proposed design modification will protect the RPS from abnormal voltage and frequency conditions which could be supplied from the power supplies and will meet certain requirements set forth by the Nuclear Regulatory Commission. The proposed design modifications will protect the RPS from sustained abnormal voltage and frequency conditions from the supplying sources.
Date:
April 29, 1982
Creator:
Selan, J.C.
System:
The UNT Digital Library
Minutes: ANSI Steering Committee on Solar Energy Standards Development
Minutes of the April 29, 1980, meeting of the American National Standards Institute steering committee on solar energy standards development are given. Attachments include correspondence from individuals and organizations which primarily describe the Solar Public Interest Coordination Committee (SPICC) and its recent activities. Also a report on the meeting of the ANSI subcommittee on international activity is attached. (WHK)
Date:
April 29, 1980
Creator:
unknown
System:
The UNT Digital Library
Development of improved iron Fischer-Tropsch catalysts
The objective of proposed research is development of catalysts with enhanced slurry phase activity and better selectivity to fuel range products, through a more detailed understanding and systematic studies of the effects of pretreatment procedures and promoters/binders (silica) on catalyst performance.
Date:
October 29, 1990
Creator:
Bukur, D.B.
System:
The UNT Digital Library
Chemical Processing Technology Quarterly Progress Report, January-March 1962
The processing of Al fuel, principally of the MTR-ETR type, is reported. Processing rate averaged 90% of flow sheet values for the entire operating period, and a U recovery of 99.85% was achieved. Aqueous Zr fuel processing studles continued with the objective of adapting the HF process to continuous dissolution-complexing in order to increase the capacity of the ICPP process while using as much existing equipment as possible to minimize costs. Good results were indicated in a 190-hr run dissolving 2% U-Zr fuel in a Monel dissolver using 4.8M HF-0.03M HNO/sub 3/ dissolvent at 200 deg F; insoluble material did not accumulate in the dissolver, although a U-containing film was formed, apparently in small, equilibrium quantity. Shorter term continuous laboratory dissolutions indicated that 4.8M acid was preferable to 10M acid for the acid feed rate/fuel surface ratios proposed, resulting in dissolver products of greater stability and higher uranium content. Additional laboratory data are presented on UF/sub 4/ hydrate form and solubility, together with maximum dissolvable U compositions with Zircaloy under various flowsheet condltions. Processing of Al alloys containing high Si was found to present no unusual problems in laboratory studies. Siliceous residues resulting from dissolution of Al-U alloys containing 2% …
Date:
June 29, 1962
Creator:
Bower, J. R.
System:
The UNT Digital Library
Magnetic field in the SSC arc quad
In part one we report on field calculations along the conductor in the end region of the SSC arc-quad. We have determined that the maximum field in the 2D section is 5.04 tesla located at the pole turn of the inner layer somewhere in the middle of the cable (strand 9)(fields are at 6500 A). At the end'' the maximum field is slightly higher 5.09 tesla located at the overpass (strand 11). The iron contribution was included assuming infinite permeability. In part two we include results of a 3D representation of the magnetic field inside the bore. The complete analysis, for which a brief description has been included here, is described elsewhere. This form for presenting the field is suitable for interfacing with other codes that make use of the 3D field components (particle tracking and stability). 69 figs.
Date:
April 29, 1991
Creator:
Caspi, S.; Helm, M. & Laslett, L.J.
System:
The UNT Digital Library
Theoretical approach for enhanced mass transfer effects in-duct flue gas desulfurization processes
Removal of sulfur dioxide (SO{sub 2}) from the flue gas of coal- burning power plants can be achieved by duct spray drying using calcium hydroxide (Ca(OH){sub 2}) slurries. A primary objective of this research was to discover the aspects of mass transfer into Ca(OH){sub 2} slurries which limit SO{sub 2} absorption. A bench- scale stirred tank reactor with a flat gas/liquid interface was used to simulate SO{sub 2} absorption in a slurry droplet. The absorption rate of SO{sub 2} from gas concentrations of 500 to 5000 ppm was measured at 55{degrees}C in clear solutions and slurries of Ca(OH){sub 2} up to 1.0 M (7 wt percent). Results are reported in terms of the enhancement factor, {O}. This research will allow prediction of conditions where the absorption of SO{sub 2} in Ca(OH){sub 2} slurries can be enhanced by changes to liquid phase constituents (under which SO{sub 2} absorption is controlled by liquid film mass transfer). Experiments in the stirred tank have shown that SO{sub 2} absorption in a 1.0 M Ca(OH){sub 2} slurry was completely dominated by gas film mass transfer with a large excess of Ca(OH){sub 2} but becomes controlled by liquid film resistance at greater than 50 percent Ca(OH){sub …
Date:
January 29, 1992
Creator:
Jozewicz, W. (Acurex Corp., Research Triangle Park, NC (United States). Environmental Systems Div.) & Rochelle, G.T. (Texas Univ., Austin, TX (United States). Dept. of Chemical Engineering)
System:
The UNT Digital Library
Preliminary designs for modular OTEC platform station-keeping subsystems. Final report. MR and S Report No. 6042-6
This volume of the report presents the results of the third through the sixth tasks of the Station Keeping Subsystem (SKSS) design studies for 10/40 MW/sub e/ capacity OTEC Modular Experiment platforms (MEP). Tasks 3 through 6 are: (3) complete preliminary designs for one SKSS for each of the two platforms (SPAR and BARGE); (4) development and testing recommendations for the MEP SKSS; (5) cost-time analysis; and (6) commercial plant recommendations. The overall conclusions and recommendations for the modular, as well as the commercial, OTEC platform station keeping subsystems are delineated. The basic design assumptions made during the process, the technical approach followed, and the results of design iterations, reliability and performance analyses are given. A complete description of the preliminary design SKSS concept is presented. The summary cost estimates for each of the alternative SKSS concepts considered are presented and a time schedule for the recommended concept is provided. The effects of varying some of the important parameters used in SKSS design on the performance and cost of the mooring system are investigated and results presented. The tests required and other developmental recommendations in order to verify and confirm the basic design assumptions are discussed. Finally, the experience gained …
Date:
February 29, 1980
Creator:
unknown
System:
The UNT Digital Library
LOFT shield tank steady state temperatures with addition of gamma and neutron shielding
The effect of introducing a neutron and gamma shield into the annulus between the reactor vessel and the shield tank is analyzed. This addition has been proposed in order to intercept neutron streaming up the annulus during nuclear operations. Its installation will require removal of approximately 20-/sup 1///sub 2/ inches of stainless steel foil insulation at the top of the annulus. The resulting conduction path is believed to result in increased water temperatures within the shield tank, possibly beyond the 150/sup 0/F limit, and/or cooling of the reactor vessel nozzles such that adverse thermal stresses would be generated. A two dimensional thermal analysis using the finite element code COUPLE/MOD2 was done for the shield tank system illustrated in the figure (1). The reactor was assumed to be at full power, 55 MW (th), with a loop flow rate of 2.15 x 10/sup 6/ lbm/hr (268.4 kg/s) at 2250 psi (15.51 MPa). Calculations indicate a steady state shield tank water temperature of 140/sup 0/F (60/sup 0/C). This is below the 150/sup 0/F (65.56/sup 0/C) limit. Also, no significant changes in thermal gradients within the nozzle or reactor vessel wall are generated. A spacer between the gamma shield and the shield tank …
Date:
September 29, 1977
Creator:
Kyllingstad, G.
System:
The UNT Digital Library
Retro-fitting a house to take advantage of cool basement walls to reduce air conditioning cost. Final report
Directions are given for a simple ventilation system to bring cool basement air to the living areas. Some results are given for electrical consumption for air conditioning before and after the retrofitting. (MHR)
Date:
September 29, 1981
Creator:
Williams, F. P.
System:
The UNT Digital Library
Special topics reports for the reference tandem mirror fusion breeder. Volume 5. Neutronic issues and optimization
More rigorous nuclear analysis, including the treatment of resonance self-shielding effects coupled with an optimization procedure, has resulted in improved performance of the Be/Li/Th blanket. Net U-233 breeding ratio has increased 36% (to 0.84) while at a U/Th ratio of 0.25 a/o energy multiplication has increased 12% (to 2.1) compared with earlier results.
Date:
March 29, 1985
Creator:
Lee, J. D. & Bandini, B. R.
System:
The UNT Digital Library
CRBRP sodium fire tests. Quarterly technical progress report, October-December 1979
The objective of the small-scale group of tests is to demonstrate that sodium will drain from the surface of the fire suppression deck into the catch pan without interference during a spill event, and to demonstrate that burning is terminated following the spill event by the accumulation of combustion products inside the drain pipes. The results of this series of tests will be used to validate the catch pan fire suppression deck design concept based on the criteria that sodium will drain freely from the surface of the fire suppression deck and that burning is terminated in an acceptably short time (less than or equal to 36 h). The objective of the large-scale group of tests is to provide experimental data on the consequences of sodium spills using prototypic leak rates and to demonstrate the effectiveness of a large-scale fire suppression Q-deck assembly.
Date:
February 29, 1980
Creator:
unknown
System:
The UNT Digital Library
Solar production of industrial process steam for the Lone Star Brewery. Conceptual design report
The project conceptual design activities are divided into six parts: Industrial Plant, Conceptual System Design, Collector Selection, Heat Transfer Fluid Selection, Site Fabrication, and Engineered Equipment. Included is an overview of the solar steam system and a brief discussion on the environmental impact of the project as well as the safety considerations of the system design. The effect of the solar system on the environment is negligible, and the safety analysis of the system indicates the considerations to be taken to minimize any potential safety hazard due to contamination of the food product or to fire. Both of these potential hazards are discussed in detail. Both the question of product contamination and the question of potential fire hazards will be presented to the industrial partner's safety committee so that the selection of the heat transfer fluid meets with their approval.
Date:
December 29, 1978
Creator:
Deffenbaugh, D.M.
System:
The UNT Digital Library
OTEC SKSS preliminary designs. Volume IV. Appendixes. Final report
This volume contains appendices to the Station Keeping Subsystem design study for the 40 MeW Modular Experiment OTEC platforms. Appendices presented include: detailed drag calculations; sample CALMS computer printouts for SPAR and BARGE static analyses; sample time domain computer printouts (Hydromechanics, Inc.) program; extreme value and fatigue load calculations; anchor design calculations; deployment calculations; bottom slope plots; time domain analysis report by Hydromechanics Inc.; detailed cost analysis; control systems study report by Sperry Systems Management; cost estimates for model basin tests; and hydrodynamic loading on the mooring cables. (WHK)
Date:
February 29, 1980
Creator:
unknown
System:
The UNT Digital Library
Monte Carlo calculations of 14-MeV neutron multiplication in thick beryllium assemblies and comparison with experimental results
Integral experiments performed at the Institute for Reactor Development at Juelich, West Germany, have raised doubts about the adequacy of current nuclear data and calculational methods in predicting neutron multiplication and leakage from beryllium assemblies bombarded with 14-MeV neutrons. Experimental values of inferred neutron multiplication were reported to be less than calculated values by approx. 25%. We have performed calculations of the experiments using the TART Monte Carlo code. The ratio of measured leakage multiplication to our calculated leakage multiplication is 0.85 for 8-cm-thick beryllium and 0.99 for 12-cm-thick beryllium. However, much uncertainty exists in the procedure leading to the stated experiment values of apparent multiplication. We also performed calculations for a series of experiments done at LLNL from 1955 to 1956. A 14-MeV neutron source was placed in the center of a cylindrical beryllium assembly 8 in. in radius and 24 in. in height. The beryllium assembly was encased in an aluminum can surrounded by a manganese bath. The ratio of experimental to calculated neutron leakage multiplication is 0.88. Much uncertainty exists in both series of experiments.
Date:
February 29, 1984
Creator:
Doyle, J. C. Jr. & Lee, J. D.
System:
The UNT Digital Library
Waste Treatment and Disposal Progress Report for August and September 1961
Work is being carried out to develop and demonstrate on pilot plant scale integrated processes for treatment and disposal of radmoactive wastes. High-level waste calcination, low-level waste treatment, economic and hazards evaluation, engineering evaluation, disposal in deep wells, disposal in natural salt formations, Clinch River studies, fundamental studies of minerals, and White Oak Creek basin study are discussed. (M.C.G.)
Date:
November 29, 1961
Creator:
Blanco, R. E. & Struxness, E. G.
System:
The UNT Digital Library
Organic Coolant Reactor Program Quarterly Report, January 1-March 31, 1962
The possible effects of a hydrogen atmosphere in reducing film deposition were studied in the large circulating loop and in rocking cell and pyrolytic capsule tests. At H/sub 2/ pressures of 200 to 400 psig no reduction in film weight deposited was observed in the loop tests, and in the pyrolytic tests film deposits were doubled. Heat conductivity of the films was much higher however. ln these high ash films the inorganic constituent was found to be alpha -Fe rather than the usual magnetite, which seems to account for the heat conductivity. Separation of benzene-insoluble material from high boiler and coolant was accomplished by centrifugation and by deposition on glass. The material was closely related to film formation. The nature of the inorganic and organic constituents of this material was examined in several analytical studies. Advances in the techniques of nuclear magnetic resonance, O/sub 2/ analysis, measurement of chromatograms, application of computers, and other methods were made. It was demonstrated by use of Fe5/sup 59/ that irradiated terphenyl under air attacks Fe rapidly and possibly the Fe is in solution as a chelate or other complex. It also was indicated by some tests that such a soluble form of Fe …
Date:
June 29, 1962
Creator:
unknown
System:
The UNT Digital Library
Energy use in office buildings. Volume 1. Analysis of 1977 office building energy use as reported in the Building Owners and Managers Association Data Base
This report presents the results of Task IA of the Energy Use in Office Buildings Project: an analysis in tabular form of the 1977 office building energy use data base of the Building Owners and Managers Association (BOMA). BOMA's approximately 4000 members directly manage over 500 million ft/sup 2/ of commercial office space, which is approximately 16% of total commercial office building space. BOMA annually collects data on office building characteristics and operating performance for presentation in its Experience Exchange Report. Data are collected from BOMA member and non-member buildings electing to participate in the reporting process; and, in addition, a number of Federal, state, and local government buildings have been participating since 1977. Summaries of the data are published by BOMA on an aggregate basis; the summaries, which are developed on a city or regional basis, provide a benchmark for use by building managers in comparing the results of specific building operations with the industry's aggregate experience. Access to the 1977 BOMA data base was obtained under a subcontract with BOMA. Data for 1342 buildings - 1059 commercial office buildings and 283 government office buildings in the United States and Canada - were delivered. Of the 1059 commercial office …
Date:
August 29, 1980
Creator:
unknown
System:
The UNT Digital Library
Experimental studies of the beam-breakup mode on ETA: comparison with theory
The beam breakup mode has been observed and measured on ETA. Comparison between the measurements and the results of a computer code indicate that the beam breakup instability will be the most important limitation on current transport thru ATA. ETA Experiments that will enable a more accurate determination of the magnitude of the instability on ATA are discussed.
Date:
January 29, 1982
Creator:
Caporaso, G.J. & Struve, K.W.
System:
The UNT Digital Library
Data Analysis Techniques for Gamma-Ray Scintillation Spectrometry
A series of computer programs are described which Were successfully applied to the reduction of pulse-height data using digital computers. Calculations carried out by these programs include: determination of pulse height vs energy response of an NaI detector; calculation of coincidence sum spectra; and the analysis of complex pulse-height spectra to obtain energies and relative intensities of individual gamma rays or relative abundances from a mixture of radionuclides. Measurement problems and instrumental requirements are discussed in detail. (auth)
Date:
May 29, 1962
Creator:
Heath, R. L.
System:
The UNT Digital Library
Underground radioactive materials in 100-H and F plants
At 100-H Area there are 13 locations and at 100-F Area 16 locations where radioactive material was deposited underground. Five of these locations, 2 at 100-H and 3 at 100-F, have been permanently terminated as burial sites in compliance with Radiation Control Standards. They contain solid waste with significant quantities of long-life radionuclides. Burial locations within the 105 Building exclusion fences were not marked with permanent posts as the exclusion fences are sufficient marking for such sites. Other locations not permanently marked were the components of the effluent systems, including the 107 retention basins, 1904 outfall structures and associated piping. Control objectives for these locations were to prevent contamination spreads and limit personnel access for several years. Similar objectives applied to locations where small quantities of liquid waste were released to ground, or small amounts of surface-contaminated materials were buried. At these locations, existing fences and radiation zone signs were left in place. The permanently posted burial grounds contain two general types of radioactive waste: neutron-activated reactor components, and surface-contaminated material and equipment. The activated components consist almost entirely of steel and aluminum. The most significant radionuclide contained in these materials is 5-year /sup 60/Co. The surface contaminants are primarily …
Date:
October 29, 1965
Creator:
Herman, G. Jr.
System:
The UNT Digital Library
ELECTROLYTIC DISSOLUTION OF NUCLEAR FUELS. PART II. NICHROME IN NITRATE SOLUTIONS
None
Date:
December 29, 1961
Creator:
Aylward, J. R. & Whitener, E. M.
System:
The UNT Digital Library
Investigation of passive cooling for hot-humid climates. Progress report No. 3
Work on getting the Brookhaven National Laboratories computer program for modeling ground coil performance operational is described. Arrangements made to sink two 40 ft vertical wells for soil temperature measurements are described. Methods for evaluating the effect of pipe diameter, length, spacing, and material were investigated. Calculation results are shown. (MHR)
Date:
April 29, 1980
Creator:
Akridge, J M
System:
The UNT Digital Library
Unfunded Mandates Reform Act: History, Impact, and Issues
This report examines debates regarding what constitutes an "unfunded federal mandate" and the Unfunded Mandates Reform Act of 1995's (UMRA) implementation. It focuses on UMRA's requirement that the Congressional Budget Office (CBO) issue written cost estimate statements for federal mandates in legislation, its procedures for raising points of order in the House and Senate concerning unfunded federal mandates in legislation, and its requirement that federal agencies prepare written cost estimate statements for federal mandates in rules. It also assesses UMRA's impact on federal mandates and arguments concerning UMRA's future, focusing on UMRA's definitions, exclusions, and exceptions which currently exempt many federal actions with potentially significant financial impacts on nonfederal entities.
Date:
August 29, 2013
Creator:
Dilger, Robert Jay & Beth, Richard S.
System:
The UNT Digital Library