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ETRANS: an energy transport system optimization code for distributed networks of solar collectors

Description: The optimization code ETRANS was developed at the Pacific Northwest Laboratory to design and estimate the costs associated with energy transport systems for distributed fields of solar collectors. The code uses frequently cited layouts for dish and trough collectors and optimizes them on a section-by-section basis. The optimal section design is that combination of pipe diameter and insulation thickness that yields the minimum annualized system-resultant cost. Among the quantities included in th… more
Date: September 1, 1980
Creator: Barnhart, J.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SM-1A PROJECT--TECHNICAL MANUAL: CHEMISTRY

Description: A manual is given of the equipment and procedures used in the Army Reactor (SM-1A) to control the water purity and makeup. In addition to a description of the primary purification control system, a discussion is presented of the water chemistry control procedures for the auxiliary systems (e.g., the spent-fuel pit, the shield tank, and the waste disposal system). (T.F.H.)
Date: September 29, 1960
Creator: Chupak, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

FUEL ELEMENT DEVELOPMENT PROGRAM FOR THE PEBBLE BED REACTOR. Final Report

Description: >The basic fuel element consisted of a uniform dispersion of fuel in a 1 1/2 inch diameter graphite sphere. Ceramic coatings for the retention of fission products were studied. It was found-that molecularly deposited'' ceramics such as alumina, siliconized silicon carbide, and pyrolytic carbon were excellent barriers to fission product leakage. The most advantageous location for ceramic coatings was found to be on the individual fuel particles, where the coating was subject to smaller forces an… more
Date: April 30, 1961
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Dynamic Simulation of Multi-Pass Pressurized Water Nuclear Power Plants by Analog Computer Techniques

Description: A kinetic model of the primary loop of a multi-pass pressurized water reactor power plant is developed to evaluate, by analog computer techniques, the transient response characteristics under conditions of steam generator load and reactor control rod perturbations. Using the 2-pass 28 Mw(t) SM-2 reactor as a typical plant, transient behavior patterns are illustrated and examined for a variety of load inputs, variations in plant constants, and analog model simplifications. (auth)
Date: June 1, 1961
Creator: Brondel, J. O.
Item Type: Refine your search to only Thesis or Dissertation
Partner: UNT Libraries Government Documents Department
open access

BOILING NUCLEAR SUPERHEATER (BONUS) POWER STATION. Supplementary Study. Extrapolation to Large Central Station Integral Nuclear Superheat Plant

Description: An evaluation was made of the maximum size plant for which the BONUS reactor plant could serve as a realistic prototype and the design changes required to increase the size and characteristics for the present BONUS design such that it could serve as a realistic prototype for the largest feasible integral-superheat reactor power plant. (M.C.G.)
Date: October 31, 1962
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Steady-State Film-Boiling Data in Rod-Bundle Geometry and Non-Equilibrium Correlation Assessment

Description: A series of 22 steady-state, rod bundle, dispersed flow film boiling experiments has been performed in the Thermal-Hydraulic Test Facility (THTF), a pressurized-water loop containing 64 full-length electrically heated rods. Test parameters in the upflow experiments cover a wide range of conditions typical of those which might be encountered during a nuclear reactor loss-of-coolant accident. Local equilibrium fluid conditions were calculated using mass and energy conservation considerations. Exp… more
Date: January 1, 1982
Creator: Yoder, G.L.; Morris, D.G.; Mullins, C.B.; Ott, L.J. & Reed, D.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Effects of intact loop hydraulic resistance of PWR LOCA behavior in scaled experimental facilities

Description: The scaling of experiments in the Water Reactor Safety Program has been on a power/volume basis. This scaling philosophy has resulted in good thermal modeling of the core, but, combined with core design considerations, compromises the modeling of the hydraulic resistance in the intact loop. Tests in LOFT, Semiscale MOD-1 and FLECHT-SET have been conducted for the purpose of determining the effect of scaling hydraulic resistance to core area ratio (low hydraulic resistance) or to core power rati… more
Date: September 1, 1977
Creator: Jacoby, M. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Lithium as a blanket coolant

Description: Recent re-assessment of tokamak reactors which move towards smaller size and lower required field strength (higher beta)/sup 2/ change the picture as regards the magnitude of MHD effects on flow resistance for lithium coolant. Perhaps the most important consequence of this as regards use of this coolant is that of clear acceptability of such effects when the flow is predominantly transverse to the magnetic field. This permits defining a blanket that consists entirely of round tubes containing t… more
Date: January 1, 1977
Creator: Wells, W.M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

75,000 KILOWATTS OF ELECTRICITY BY NUCLEAR FISSION AT THE HALLAM NUCLEAR POWER FACILITY

Description: For presentation at ASCE Convention in Reno, Nevada on Thursday, June 23, 1860. A description of the Hallam Nuclear Power Facslity is presented. The history of the project, program participants, site description, component development program, reaetor building, reactor structure, reactor core, sodium systems, instrumentation and control, fuel and component handling, auxsilary sustems, special design features, and advantages of sodium graphite reactor systems are discussed. (M.C.G.)
Date: January 1, 1960
Creator: Gronemeyer, F.C. & Merryman, J.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Barriers to the Application of High-Temperature Coolants in Hybrid Electric Vehicles

Description: This study was performed by the Oak Ridge National Laboratory (ORNL) to identify practical approaches, technical barriers, and cost impacts to achieving high-temperature coolant operation for certain traction drive subassemblies and components of hybrid electric vehicles (HEV). HEVs are unique in their need for the cooling of certain dedicated-traction drive subassemblies/components that include the electric motor(s), generators(s), inverter, dc converter (where applicable), and dc-link capacit… more
Date: September 30, 2006
Creator: Hsu, J.S.; Staunton, M.R. & Starke, M.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

PWR Facility Dose Modeling Using MCNP5 and the CADIS/ADVANTG Variance-Reduction Methodology

Description: The feasibility of modeling a pressurized-water-reactor (PWR) facility and calculating dose rates at all locations within the containment and adjoining structures using MCNP5 with mesh tallies is presented. Calculations of dose rates resulting from neutron and photon sources from the reactor (operating and shut down for various periods) and the spent fuel pool, as well as for the photon source from the primary coolant loop, were all of interest. Identification of the PWR facility, development o… more
Date: September 1, 2007
Creator: Blakeman, Edward D; Peplow, Douglas E.; Wagner, John C; Murphy, Brian D & Mueller, Don
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Development and testing of a diagnostic system for intelligen distributed control at EBR-2

Description: A diagnostic system is under development for demonstration of Intelligent Distributed Control at the Experimental Breeder Reactor (EBR--II). In the first phase of the project a diagnostic system is being developed for the EBR-II steam plant based on the DISYS expert systems approach. Current testing uses recorded plant data and data from simulated plant faults. The dynamical simulation of the EBR-II steam plant uses the Babcock and Wilcox (B W) Modular Modeling System (MMS). At EBR-II the diagn… more
Date: January 1, 1990
Creator: Edwards, R.M.; Ruhl, D.W.; Klevans, E.H. & Robinson, G.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Fluid forces on two circular cylinders in crossflow

Description: Fluid excitation forces are measured in a water loop for two circular cylinders arranged in tandem and normal to flow. The Strouhal number and fluctuating drag and lift coefficients for both cylinders are presented for various spacings and incoming flow conditions. Results show the effects of Reynolds number, pitch ratio, and upstream turbulence on the fluid excitation forces.
Date: June 1, 1985
Creator: Jendrzejczyk, J.A. & Chen, S.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Simulation of Natural Convection in a Rectangular Loop Using Finite Elements

Description: A two-dimensional finite-element analysis of natural convection in a rectangular loop is presented. A psi-omega formulation of the Boussinesque approximation to the Navier-Stokes equation is solved by the false transient technique. Streamlines and isotherms at Ra = 10/sup 4/ are shown for three different modes of heating. The results indicate that corner effects should be considered when modeling flow patterns in thermosyphons.
Date: January 1, 1984
Creator: Pepper, D. W.; Hamm, L. L. & Kehoe, A. B.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

ORNL rod-bundle heat-transfer test data. Volume 6. Thermal-hydraulic test facility experimental data report for test 3. 05. 5B - double-ended cold-leg break simulation

Description: Thermal-Hydraulic Test Facility (THTF) Test 3.05.5B was conducted by members of the ORNL PWR Blowdown Heat Transfer Separate-Effects Program on July 3, 1980. The objective of the program is to investigate heat transfer phenomena believed to occur in PWRs during accidents, including small and large break loss-of-coolant accidents. Test 3.05.5B was designed to provide transient thermal-hydraulics data in rod bundle geometry under reactor accident-type conditions. Reduced instrument responses are … more
Date: May 18, 1982
Creator: Mullins, C. B.; Felde, D. K.; Sutton, A. G.; Gould, S. S.; Morris, D. G.; Robinson, J. J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Fusion blankets for catalyzed D--D and D--/sup 3/He reactors

Description: Blanket designs are presented for catalyzed D-D (Cat-D) and D-He/sup 3/ fusion reactors. Because of relatively low neutron wall loads and the flexibility due to non-tritium breeding, blankets potentially should operate for reactor life-times of approximately 30 years. Unscheduled replacement of failed blanket modules should be relatively rapid, due to very low residual activity, by operators working either through access ports in the shield (option 1) or directly in the plasma chamber (option 2… more
Date: January 1, 1977
Creator: Fillo, J.A. & Powell, J.R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Thermal and hydraulic analyses of TFTR cooling water system and magnetic field coils

Description: The TFTR toroidal field coils, ohmic heating, hybrid and equilibrium field coils are cooled by water from the machine area cooling water system. The system has the following major equipment and capacities: flow rate of 3600 gpm; ballast tank volume of 5500 gal; pumps of 70.4 m head; chiller refrigeration rating of 3300 tons and connecting pipe of 45.7 cm I.D. The performance of the closed loop system was analyzed and found to be adequate for the thermal loads. The field coils were analyzed with… more
Date: October 1, 1975
Creator: Lee, A. Y.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

High-Temperature High-Power Packaging Techniques for HEV Traction Applications

Description: A key issue associated with the wider adoption of hybrid-electric vehicles (HEV) and plug in hybrid-electric vehicles (PHEV) is the implementation of the power electronic systems that are required in these products [1]. To date, many consumers find the adoption of these technologies problematic based on a financial analysis of the initial cost versus the savings available from reduced fuel consumption. Therefore, one of the primary industry goals is the reduction in the price of these vehicles … more
Date: November 30, 2006
Creator: Barlow, F.D. & Elshabini, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

High temperature, high pressure gas loop - the Component Flow Test Loop (CFTL)

Description: The high-pressure, high-temperature, gas-circulating Component Flow Test Loop located at Oak Ridge National Laboratory was designed and constructed utilizing Section III of the ASME Boiler and Pressure Vessel Code. The quality assurance program for operating and testing is also based on applicable ASME standards. Power to a total of 5 MW is available to the test section, and an air-cooled heat exchanger rated at 4.4 MW serves as heat sink. The three gas-bearing, completely enclosed gas circulat… more
Date: January 1, 1984
Creator: Gat, U.; Sanders, J.P. & Young, H.C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Gas-cooled fast reactor program. Progress report, January 1, 1980-June 30, 1981

Description: Since the national Gas-Cooled Fast Breeder Reactor Program has been terminated, this document is the last progress report until reinstatement. It is divided into three sections: Core Flow Test Loop, GCFR shielding and physics, and GCFR pressure vessel and closure studies. (DLC)
Date: September 1, 1981
Creator: Kasten, P. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design and testing of a superfluid liquid helium cooling loop

Description: This paper describes the design and preliminary testing of a cryogenic cooling loop that uses a thermomechanical pump to circulate superfluid liquid helium. The cooling loop test apparatus is designed to prove forced liquid helium flow concepts that will be used on the Astromag superconducting magnet facility. 3 refs., 2 figs.
Date: July 1, 1989
Creator: Gavin, L. M.; Green, M. A.; Levin, S. M.; Smoot, G. F. & Witebsky, C.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Revised evaluation of steam generator testing alternatives

Description: A scoping evaluation was made of various facility alternatives for test of LMFBR prototype steam generators and models. Recommendations are given for modifications to EBR-II and SCTI (Sodium Components Test Installation) for prototype SG testing, and for few-tube model testing. (DLC)
Date: unknown
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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