724 Matching Results

Search Results

Advanced search parameters have been applied.

in subjects: "Coolant Loops"

open access

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

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: Report

Partner: UNT Libraries Government Documents Department

open access

SM-1A PROJECT--TECHNICAL MANUAL: CHEMISTRY

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: Report

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

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: Report

Partner: UNT Libraries Government Documents Department

open access

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

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: Article

Partner: UNT Libraries Government Documents Department

open access

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

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: Report

Partner: UNT Libraries Government Documents Department

open access

Lithium as a blanket coolant

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: Article

Partner: UNT Libraries Government Documents Department

open access

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

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: Report

Partner: UNT Libraries Government Documents Department

open access

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

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: Report

Partner: UNT Libraries Government Documents Department

open access

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

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: Article

Partner: UNT Libraries Government Documents Department

open access

Fluid forces on two circular cylinders in crossflow

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: Report

Partner: UNT Libraries Government Documents Department

open access

Simulation of Natural Convection in a Rectangular Loop Using Finite Elements

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: Article

Partner: UNT Libraries Government Documents Department

open access

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

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: Article

Partner: UNT Libraries Government Documents Department

open access

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

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: Report

Partner: UNT Libraries Government Documents Department

open access

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

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: Report

Partner: UNT Libraries Government Documents Department

open access

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

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: Article

Partner: UNT Libraries Government Documents Department

open access

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

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: Report

Partner: UNT Libraries Government Documents Department

open access

Design and testing of a superfluid liquid helium cooling loop

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: Article

Partner: UNT Libraries Government Documents Department

open access

Revised evaluation of steam generator testing alternatives

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: Report

Partner: UNT Libraries Government Documents Department

open access

Computational model for optimizing longitudinal fin heat transfer in laminar internal flows

Optimal configurations are identified, based on a numerical model, for fully developed laminar internal flows whose base boundary walls have perpendicular fins extending longitudinally into the fluid. The optimum coolant flow channel, formed between each fin, has an aspect ratio dependent on the coolant to wall thermal conductivity ratio and on the fin to channel width ratio, which is optimally about unity. A base thickness exists which minimizes the base hot-spot temperature, and its value is … more

Date: November 1, 1990

Creator: Landram, C. S.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Investigation of wellbore cooling by circulation and fluid penetration into the formation using a wellbore thermal simulator computer code

The high temperatures of geothermal wells present severe problems for drilling, logging, and developing these reservoirs. Cooling the wellbore is perhaps the most common method to solve these problems. However, it is usually not clear what may be the most effective wellbore cooling mechanism for a given well. In this paper, wellbore cooling by the use of circulation or by fluid injection into the surrounding rock is investigated using a wellbore thermal simulator computer code. Short circulatio… more

Date: January 1, 1987

Creator: Duda, L.E.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Measurements and calculations of water velocity, momentum flux, and related flow parameters obtaned from single-phase water integral acceptance tests of the PKL instrumented spool pieces

The operation of the emergency core cooling system and its related steam-binding problems in pressurized water reactors is the subject of a cooperative study by the United States, Germany, and Japan. Lawrence Livermore Laboratory and EG and G, Inc., San Ramon Operations, are responsible for the design, hardware, and software of the 80.8-mm and 113-mm spool piece measurement systems for the German Primarkreislauf (PKL) Test Facility at Kraftwerk Union in Erlangen, West Germany. This work was don… more

Date: October 9, 1979

Creator: Stein, W.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Natural circulation in simulated LMFBR fuel assemblies

Natural circulation experiments have been performed using simulated liquid metal fast breeder reactor fuel assemblies in the Thermal-Hydraulic Out-of-Reactor Safety (THORS) facility, an engineering-scale sodium loop. Objective of these tests has been to provide experimental data under conditions that might be encountered during a partial or total loss of the shutdown heat removal system (SHRS) in a reactor. The experiments have included single- and two-phase tests under quasi-steady and transie… more

Date: January 1, 1985

Creator: Levin, A. E.; Carbajo, J. J.; Lloyd, D. B.; Montgomery, B. H.; Rose, S. D. & Wantland, J. L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

High-temperature helium-loop facility

The high-temperature helium loop is a facility for materials testing in ultrapure helium gas at high temperatures. The closed loop system is capable of recirculating high-purity helium or helium with controlled impurities. The gas loop maximum operating conditions are as follows: 300 psi pressure, 500 lb/h flow rate, and 2100/sup 0/F temperature. The two test sections can accept samples up to 3.5 in. diameter and 5 ft long. The gas loop is fully instrumented to continuously monitor all paramete… more

Date: September 1, 1981

Creator: Tokarz, R. D.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Status of HTGR technology development and demonstration

Several HGTR items which require thorough testing include the core support and pads, vessel insulation and liner, and graphite fuel blocks. Tests which are to be conducted in the Component Flow Test Loop are discussed. The neutron streaming experiment at the Tower Shielding Facility is described. Materials and fuels development studies are also discussed. (DLC)

Date: January 1, 1983

Creator: Trauger, D.B.

Item Type: Article

Partner: UNT Libraries Government Documents Department