8 Matching Results

Search Results

Advanced search parameters have been applied.
in subjects: "Temperature Distribution"  
Results: 1 - 8
open access

LOFT shield tank steady state temperatures with addition of gamma and neutron shielding

Description: 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, poss… more
Date: September 29, 1977
Creator: Kyllingstad, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Finite difference program for calculating hydride bed wall temperature profiles

Description: A QuickBASIC finite difference program was written for calculating one dimensional temperature profiles in up to two media with flat, cylindrical, or spherical geometries. The development of the program was motivated by the need to calculate maximum temperature differences across the walls of the Tritium metal hydrides beds for thermal fatigue analysis. The purpose of this report is to document the equations and the computer program used to calculate transient wall temperatures in stainless ste… more
Date: October 29, 1992
Creator: Klein, J. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Development fo the Instrumentation and Modeling for Heat Transfer Characteristice in CFBC

Description: This technical report summarizes the research conducted and results obtained during the period beginning April 1, 1999 to September 30, 1999. Numerical simulation was used to predict the air velocity and pressure, temperature, and heat transfer characteristics in the CFB system. The radial air velocities changed frequently because of the voidage and gas pressure drop that caused in the heat transfer probe inlet level (k=23). The lower pressure zone was formed near the chamber's center region. T… more
Date: September 29, 1999
Creator: Lee, Seong W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Development of the Instrumentation and Modeling for Heat Transfer Characteristics in CFBC

Description: This technical report summarizes the research conducted and results obtained during the period beginning October 1, 1999 to March 31, 2000. Heat transfer characteristics study and experimental work were continued using the bench-scale CFB system with the heat transfer probe. A copper tube with thermocouples was used as the heat transfer probe which was convenient to measure the temperature changes at different locations of the bed. The heat transfer coefficient at different locations of the hea… more
Date: March 29, 2000
Creator: Lee, Seong E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Improved Materials for High-Temperature Black Liquor Gasification

Description: The laboratory immersion test system built and operated at ORNL was found to successfully screen samples from numerous refractory suppliers, including both commercially available and experimental materials. This system was found to provide an accurate prediction of how these materials would perform in the actual gasifier environment. Test materials included mullites, alumino-silicate bricks, fusion-cast aluminas, alumina-based and chrome-containing mortars, phosphate-bonded mortars, coated samp… more
Date: June 29, 2006
Creator: Keiser, J. R.; Hemrick, J. G.; Gorog, J. P. & Leary, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Breeder Reactor Fuel Development in the USA

Description: An overview of the National LMFBR Fuel Development Program is presented which includes a brief review of fuel performance concerns and issues and highlights of current fuel testing activities in EBR-II and the FFTF.
Date: March 29, 1982
Creator: Gibby, R. L. & Mahagin, D. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Radionuclide methods validation with FSV [Fort St. Vrain] data

Description: As part of the radionuclide methods verification program at GA, a fuel performance analysis of the Fort St. Vrain (FSV) core was performed using the reference fuel performance and fission gas release models. The purpose of the analysis was to predict the fuel and graphite temperature distributions, fuel particle failure, and fission gas release as a function of time, and to compare the predicted fission gas release with data taken as part of the FSV radiochemistry surveillance program. The anal… more
Date: September 29, 1989
Creator: Jovanovic, V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

DEVELOPMENT OF A VALIDATED MODEL FOR USE IN MINIMIZING NOx EMISSIONS AND MAXIMIZING CARBON UTILIZATION WHEN CO-FIRING BIOMASS WITH COAL

Description: This is the ninth Quarterly Technical Report for DOE Cooperative Agreement No. DE-FC26-00NT40895. A statement of the project objectives is included in the Introduction of this report. The pilot-scale testing phase of the project has been completed. Calculations are essentially completed for implementing a modeling approach to combine reaction times and temperature distributions from computational fluid dynamic models of the pilot-scale combustion furnace with char burnout and chemical reaction … more
Date: January 29, 2003
Creator: Felix, Larry G. & Bush, P. Vann
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
Back to Top of Screen