Search Results

Advanced search parameters have been applied.
open access

Recent High Heat Flux Tests on W-Rod-Armored Mockups

Description: In the authors initial high heat flux tests on small mockups armored with W rods, done in the small electron beam facility (EBTS) at Sandia National Laboratories, the mockups exhibited excellent thermal performance. However, to reach high heat fluxes, they reduced the heated area to only a portion ({approximately}25%) of the sample. They have now begun tests in their larger electron beam facility, EB 1200, where the available power (1.2 MW) is more than enough to heat the entire surface area of… more
Date: July 18, 2000
Creator: NYGREN,RICHARD E.; YOUCHISON,DENNIS L.; MCDONALD,JIMMIE M.; LUTZ,THOMAS J. & MISZKIEL,MARK E.
Partner: UNT Libraries Government Documents Department
open access

Measurements of thermal accommodation coefficients.

Description: A previously-developed experimental facility has been used to determine gas-surface thermal accommodation coefficients from the pressure dependence of the heat flux between parallel plates of similar material but different surface finish. Heat flux between the plates is inferred from measurements of temperature drop between the plate surface and an adjacent temperature-controlled water bath. Thermal accommodation measurements were determined from the pressure dependence of the heat flux for a f… more
Date: October 1, 2005
Creator: Rader, Daniel John; Castaneda, Jaime N.; Torczynski, John R.; Grasser, Thomas W. & Trott, Wayne Merle
Partner: UNT Libraries Government Documents Department
open access

Uncertainty analysis of steady state incident heat flux measurements in hydrocarbon fuel fires.

Description: The objective of this report is to develop uncertainty estimates for three heat flux measurement techniques used for the measurement of incident heat flux in a combined radiative and convective environment. This is related to the measurement of heat flux to objects placed inside hydrocarbon fuel (diesel, JP-8 jet fuel) fires, which is very difficult to make accurately (e.g., less than 10%). Three methods will be discussed: a Schmidt-Boelter heat flux gage; a calorimeter and inverse heat conduct… more
Date: December 1, 2005
Creator: Nakos, James Thomas
Partner: UNT Libraries Government Documents Department
open access

Microscale rarefied gas dynamics and surface interactions for EUVL and MEMS applications.

Description: A combined experimental/modeling study was conducted to better understand the critical role of gas-surface interactions in rarefied gas flows. An experimental chamber and supporting diagnostics were designed and assembled to allow simultaneous measurements of gas heat flux and inter-plate gas density profiles in an axisymmetric, parallel-plate geometry. Measurements of gas density profiles and heat flux are made under identical conditions, eliminating an important limitation of earlier studies.… more
Date: November 1, 2004
Creator: Gallis, Michail A.; Rader, Daniel John; Castaneda, Jaime N.; Torczynski, John R.; Grasser, Thomas W. & Trott, Wayne Merle
Partner: UNT Libraries Government Documents Department
open access

Transition and Film Boiling Data at 600, 1000, and 1400 PSIA in Forced Convection Heat Transfer to Water

Description: Summary: Data were obtained in a two-road test section which consisted of two 7/16-inch diameter heater rods inside a roughly rectangular flow area. The heated length of the rods was 30 inches, with a 15-inch unheated calming length preceding it. Heater wall temperatures were recorded while the heater tubes were trans-versing the critical heat flux and transition boiling; these temperatures were used to calculate heat transfer coefficients. The following general results were obtaining: (a)… more
Date: March 1964
Creator: Hench, J. E.
Partner: UNT Libraries Government Documents Department
open access

Multirod (Four Rod) Critical Heat Flux at 1000 PSIA

Description: Technical report describing the four-rod heat flux experiments that are a part of a continuing program of study of the critical heat flux, or burnout phenomenon in order that water cooled reactors can be designed with a maximum of safety and efficiency. During heat transfer with boiling, there is a particular heat flux, for a given set of flow conditions and geometry, above which the nucleate boiling process begins to break down. This breakdown of the nucleate boiling process is known as burno… more
Date: September 1963
Creator: Hench, John E.
Partner: UNT Libraries Government Documents Department
open access

8. Innovative Technologies: Two-Phase Heat Transfer in Water-Based Nanofluids for Nuclear Applications Final Report

Description: Abstract Nanofluids are colloidal dispersions of nanoparticles in water. Many studies have reported very significant enhancement (up to 200%) of the Critical Heat Flux (CHF) in pool boiling of nanofluids (You et al. 2003, Vassallo et al. 2004, Bang and Chang 2005, Kim et al. 2006, Kim et al. 2007). These observations have generated considerable interest in nanofluids as potential coolants for more compact and efficient thermal management systems. Potential Light Water Reactor applications inclu… more
Date: July 31, 2009
Creator: Buongiorno, Jacopo & Hu, Lin-wen
Partner: UNT Libraries Government Documents Department
open access

Transition Boiling Heat Transfer Program; Fourth Quarterly Progress Report, October - December 1963

Description: Summary: Heat transfer tests employing the two-rod test section without film tripping devices have been completed. Representations defining critical heat flux, transition boiling and film boiling behavior at high pressures and over a steam quality range of 25 to 90 percent are shown. Fabrication of a new observational test section was completed and initial test results with high-speed motion pictures were obtained. A test loop instability which was found to affect transition boiling behavio… more
Date: January 1, 1964
Creator: Quinn, E. P.
Partner: UNT Libraries Government Documents Department
open access

Transition Boiling Heat Transfer Program; Third Quarterly Progress Report, July - September 1963

Description: Summary: Initial critical heat flux, transition boiling temperature fluctuation, and film boiling coefficient data have been obtained on a two-rod cluster assembly at 1000 psia and 25 to 90 percent steam qualities. A representation showing the range of critical heat flux data is presented. Typical temperature recordings which indicate transition and film boiling behavior are shown. Fabrication of a new high pressure observational test section is nearly complete. An optical table and illuminatio… more
Date: October 1, 1963
Creator: Quinn, E. P.
Partner: UNT Libraries Government Documents Department
open access

Transition Boiling Heat Transfer Program; Second Quarterly Progress Report, April - June 1963

Description: Introduction: The Transition Boiling Heat Transfer Program is sponsored jointly by the USAEC and Euroatom and is being conducted by the General Electric Company. The work commenced on this program February 11, 1963. The objective of this program is to perform basic investigation and measurement of the transition boiling regime in high pressure bulk boiling water flows, with particular emphasis i the high range of steam qualities.
Date: July 1, 1963
Creator: Quinn, E. P.
Partner: UNT Libraries Government Documents Department
open access

Assessment of simulation predictions of hydrocarbon pool fire tests.

Description: An uncertainty quantification (UQ) analysis is performed on the fuel regression rate model within SIERRA/Fuego by comparing to a series of hydrocarbon tests performed in the Thermal Test Complex. The fuels used for comparison for the fuel regression rate model include methanol, ethanol, JP8, and heptane. The recently implemented flamelet combustion model is also assessed with a limited comparison to data involving measurements of temperature and relative mole fractions within a 2-m diameter met… more
Date: April 1, 2010
Creator: Luketa-Hanlin, Anay Josephine
Partner: UNT Libraries Government Documents Department
open access

Thermal Hydraulic Analysis of Fire Divertor

Description: The Fusion Ignition Research Experiment (FIRE) is being designed as a next step in the US magnetic fusion program. The FIRE tokamak has a major radius of 2 m, a minor radius of 0.525 m, and liquid nitrogen cooled copper coils. The aim is to produce a pulse length of 20 s with a plasma current of 6.6 MA and with alpha dominated heating. The outer divertor and baffle of FIRE are water cooled. The worst thermal condition for the outer divertor and baffle is the baseline D-T operating mode (10 T, 6… more
Date: October 2000
Creator: Baxi, C. B.; Ulrickson, M. A.; Driemeyer, D. E. & Heitzenroeder, P.
Partner: UNT Libraries Government Documents Department
open access

Development of an Extreme Environment Materials Research Facility at Princeton

Description: The need for a fundamental understanding of material response to a neutron and/or high heat flux environment can yield development of improved materials and operations with existing materials. Such understanding has numerous applications in fields such as nuclear power (for the current fleet and future fission and fusion reactors), aerospace, and other research fields (e.g., high-intensity proton accelerator facilities for high energy physics research). A proposal has been advanced to develop a… more
Date: November 17, 2010
Creator: Cohen, A. B.; Tully, C. G.; Austin, R.; Calaprice, F.; McDonald, K.; Ascione, G. et al.
Partner: UNT Libraries Government Documents Department
open access

Annual Progress Report of Methods to Increase Burnout Heat Transfer

Description: "Acoustic energy generated by mechanical or electrical signals and its effect on pool boiling of isopropanol were studied. Daring the course of the investigation, a method was devised to determine the amount of heat-transfer surface wetted by the boiling isopropanol. Plots of heat flux versus temperature difference for each frequency showed that the acoustic energy did not significantly affect the heat flux at burnout, but slightly increased the critical temperature difference. No general effec… more
Date: September 30, 1960
Creator: Markels, Michael; Durfee, Robert L. & Richardson, Robert
Partner: UNT Libraries Government Documents Department
open access

The Location of the Maximum Temperature on the Cutting Edges of a Drill

Description: This study analyzes the temperature profile along the cutting edges of a drill and describes how the temperature on the chisel edge can exceed the temperature on the primary cutting edges. A finite element model predicts the temperature distribution in the drill, where the heat flux loads applied to the finite element model are determined from analytical equations. The model for the heat flux loads considers both the heat generated on the shear plane and the heat generated on the rake face of t… more
Date: January 7, 2005
Creator: Bono, M J & Ni, J
Partner: UNT Libraries Government Documents Department
open access

Critical Heat Flux for Downward-Facing Boiling on a Coated Hemispherical Vessel Surrounded by an Insulation Structure

Description: An experimental study was performed to evaluate the effects of surface coating and an enhanced insulation structure on the downward facing boiling process and the critical heat flux on the outer surface of a hemispherical vessel. Steady-state boiling tests were conducted in the Subscale Boundary Layer Boiling (SBLB) facility using an enhanced vessel/insulation design for the cases with and without vessel coatings. Based on the boiling data, CHF correlations were obtained for both plain and coat… more
Date: May 1, 2005
Creator: Yang, J.; Cheung, F. B.; Rempe, J. L.; Suh, K. Y. & Kim, S. B.
Partner: UNT Libraries Government Documents Department
open access

Critical Heat Flux in Inclined Rectangular Narrow Gaps

Description: In light of the TMI-2 accident, in which the reactor vessel lower head survived the attack by molten core material, the in-vessel retention strategy was suggested to benefit from cooling the debris through a gap between the lower head and the core material. The GAMMA 1D (Gap Apparatus Mitigating Melt Attack One Dimensional) tests were conducted to investigate the critical heat flux (CHF) in narrow gaps with varying surface orientations. The CHF in an inclined gap, especially in case of the down… more
Date: June 1, 2004
Creator: Kim, Jeong J.; Kim, Yong H.; Kim, Seong J.; Noh, Sang W.; Suh, Kune Y.; Rempe, Joy L. et al.
Partner: UNT Libraries Government Documents Department
open access

FILM-30: A Heat Transfer Properties Code for Water Coolant

Description: A FORTRAN computer code has been written to calculate the heat transfer properties at the wetted perimeter of a coolant channel when provided the bulk water conditions. This computer code is titled FILM-30 and the code calculates its heat transfer properties by using the following correlations: (1) Sieder-Tate: forced convection, (2) Bergles-Rohsenow: onset to nucleate boiling, (3) Bergles-Rohsenow: partially developed nucleate boiling, (4) Araki: fully developed nucleate boiling, (5) Tong-75: … more
Date: February 1, 2001
Creator: Marshall, Theron D.
Partner: UNT Libraries Government Documents Department
open access

On the Jarzynski relation for dissipative quantumdynamics

Description: In this note, we will discuss how to compactly express the Jarzynski identity for an open quantum system with dissipative dynamics. In quantum dynamics we must avoid explicitly measuring the work directly, which is tantamount to continuously monitoring the state of the system, and instead measure the heat ?ow from the environment. These measurements can be concisely represented with Hermitian map superoperators, which provide a convenient and compact representations of correlation functions and… more
Date: October 30, 2008
Creator: Crooks, Gavin E
Partner: UNT Libraries Government Documents Department
Back to Top of Screen