Eine Plattform für die Wissenschaft: Bauingenieurwesen, Architektur und Urbanistik
Eine Plattform für die Wissenschaft: Bauingenieurwesen, Architektur und Urbanistik
Sensitivity Analysis for USINT - A Program for Calculating Heat and Mass Transfer in Concrete Subjected to High Heat Fluxes
Program USINT was developed at Sandia National Laboratories for calculating heat and mass transfer in concrete subjected to high heat fluxes. The mathematical model incorporated into Program USINT contains at least fifteen parameters. This report presents a sensitivity study for Program USINT to provide information regarding the relative importance of these parameters. Previously, a case was solved with a prescribed temperature boundary condition. This temperature history is near the heated surface of a concrete specimen. The particular temperature history utilized was measured at Hanford Engineering Development Laboratory (HEDL). This case was utilized to obtain the sensitivity coefficients calculated herein.
Sensitivity Analysis for USINT - A Program for Calculating Heat and Mass Transfer in Concrete Subjected to High Heat Fluxes
Program USINT was developed at Sandia National Laboratories for calculating heat and mass transfer in concrete subjected to high heat fluxes. The mathematical model incorporated into Program USINT contains at least fifteen parameters. This report presents a sensitivity study for Program USINT to provide information regarding the relative importance of these parameters. Previously, a case was solved with a prescribed temperature boundary condition. This temperature history is near the heated surface of a concrete specimen. The particular temperature history utilized was measured at Hanford Engineering Development Laboratory (HEDL). This case was utilized to obtain the sensitivity coefficients calculated herein.
Sensitivity Analysis for USINT - A Program for Calculating Heat and Mass Transfer in Concrete Subjected to High Heat Fluxes
J. V. Beck (Autor:in)
1981
106 pages
Report
Keine Angabe
Englisch
Reactor Engineering & Nuclear Power Plants , Construction Equipment, Materials, & Supplies , Nuclear reactor accidents , Liquid metal cooled reactors , Concretes , Reaction kinetics , Heat flux , Mass transfer , Heat transfer , Mathematical models , Loss of coolant , Breeder reactors , USINT computer program
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