				Search Options
Index \| Site Map \| FAQ \| Facility Info \| Reading Rm \| New \| Help \| Glossary \| Contact Us

Data Analyses for Nevada Test Site (NTS) Premixed Combustion Tests (NUREG/CR-4138)

On this page:

Publication Information
Abstract

Download complete document

The following links on this page are to documents in Adobe Portable Document Format (PDF). See our Plugins, Viewers, and Other Tools page for more information. For successful viewing of PDF documents on our site please be sure to use the latest version of Adobe.

NUREG/CR-4138 (PDF - 9.73 MB)

Publication Information

May 1985

Sandia National Laboratories
Albuquerque, NM 87185

Operated by
Sandia Corporation for the
U.S. Department of Energy

Prepared for
Division of Accident Evaluation
and
Division of Engineering Technology
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, D.C. 20555
NRC FIN Nos. A1246, A1270

Availability Notice

Abstract

This report provides results from an in-depth analysis of twenty-one of the twenty-four premixed large-scale combustion experiments sponsored by the U. S. Nuclear Regulatory Commission (NRC) and the Electric Power Research Institute (EPRI) and conducted by EG&G at the Nevada Test Site (NTS). These experiments were performed in a 2048 cubic meter spherical vessel (hydrogen dewar) with mixtures of hydrogen, steam, and air ignited by glow plugs or heated resistance coils. Hydrogen concentrations ranged from 5 to 13% (by volume) and steam concentrations from 4 to 40%. Several tests also incorporated spray systems and/or fans which enhanced the combustion rate and significantly altered the postcombustion gas cooling.

In this work, data provided by EPRI from. instrumentation designed to characterize the. thermal environment in the dewar during and following combustion have been evaluated. The data reduction package SMOKE has been used to process data from thin-film gauges, Gardon and Schmidt-Boelter heat flux gauges, capacitance calorimeters, gas and wall thermocouples, arid pressure sensors. Local measurements..of the heat transfer are provided from the calorimetry, and global averages are inferred from the pressure. Instrumentation "goodness" for each test is assessed based on the raw data and on comparisons of local and global results. Graphical and tabular results are provided for. each test, and trends observed from the results are reported. This information should be useful for benchmarking existing computer codes used in modeling nuclear containment and associated safety-related equipment response to. degraded-core accidents and for improving combustion and heat transfer models Currently used in these computer simulations.