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in creator/contributor: "Viskanta, R."  
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Heat transfer to water from a vertical tube bundle under natural-circulation conditions. [PWR; BWR]

Description: The natural circulation heat transfer data for longitudinal flow of water outside a vertical rod bundle are needed for developing correlations which can be used in best estimate computer codes to model thermal-hydraulic behavior of nuclear reactor cores under accident or shutdown conditions. The heat transfer coefficient between the fuel rod surface and the coolant is the key parameter required to predict the fuel temperature. Because of the absence of the required heat transfer coefficient dat… more
Date: January 1, 1983
Creator: Gruszczynski, M.J. & Viskanta, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Heat Transfer With Laminar Flow in Concentric Annuli With Constant and Arbitrary Variable Axial Wall Temperature

Description: An analysis has been performed to determine the heat transfer characteristics for laminar forced-convection flow in a concentric annulus with prescribed surface temperatures. Three distinct problems were considered: (a) wall temperature prescribed at both the inside and outside wall; (b) inside wall temperature prescribed and the outside wall insulated; and (c) inside wall insulated and outside wall temperature prescribed. The solution for temperature distribution was similar to that obtained b… more
Date: December 1, 1961
Creator: Viskanta, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

THE AXISYMMETRIC FREE-CONVECTION HEAT TRANSFER ALONG A VERTICAL THIN CYLINDER WITH CONSTANT SURFACE TEMPERATURE

Description: Laminar free-convection flow produced by a heated, vertical, circular cylinder for which the temperature at the outer surface of the cylinder is assumed to be uniform is analyzed. The solution of the boundary-layer equations was obtained by the perturbation method of Sparrow and Gregg, which is valid only for small values of the axial distance parameter xi ; and the integral method of Hama et al., for large values of the parameter xi . Heat-transfer results were calculated for Prandtl numbers (… more
Date: January 1, 1963
Creator: Viskanta, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SCDAP/RELAP5 independent peer review

Description: The SCDAP/RELAP5 code has been developed for best-estimate transient simulation of light-water-reactor coolant systems during severe accidents. The newest version of the code is SCDAP/RELAP5/MOD3. The US Nuclear Regulatory Commission (NRC) decided that there was a need for a broad technical review of the code by recognized experts to determine overall technical adequacy, even though the code is still under development. For this purpose, an eight-member SCDAP/RELAP5 Peer Review Committee was org… more
Date: January 1993
Creator: Corradini, M. L.; Dhir, V. K.; Haste, T. J.; Heames, T. J.; Jenks, R. P.; Kelly, J. E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

MELCOR Peer Review

Description: MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. The newest version of MELCOR is Version 1.8.1, July 1991. MELCOR development has reached the point that the United States Nuclear Regulatory Commission sponsored a broad technical review by recognized experts to determine or confirm the technical adequacy of the code for the serious and complex analyses it is expected to perform. For this pur… more
Date: March 1992
Creator: Boyack, B. E.; Dhir, V. K.; Gieseke, J. A.; Haste, T. J.; Kenton, M. A.; Khatib-Rahbar, M. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

SOME HEAT TRANSFER AND FLUID FLOW CONSIDERATIONS FOR A PACKED-BED FUEL ELEMENT

Description: The problem of heat transfer and fluid flow in a heatgenerating porous media was studied analytically. The study was limited to the range of parameters of interest to the packed-bed fuel element concept. The available heat transfer and pressure drop correlations are reviewed. A system of partial differential equations which govern the velocity and temperature fields in an isotropic porous media was derived. Steady-state temperature distribution in a one-dimensional packed bed was studied, and a… more
Date: May 1, 1961
Creator: Viskanta, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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