NDLI: Air Ingress Analysis: Computational Fluid Dynamics Models

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Chang, H. Oh Eung, S. Kim
Copyright Year	2010
Abstract	Idaho National Laboratory (INL), under the auspices of the U.S. Department of Energy (DOE), is performing research and development that focuses on key phenomena important during potential scenarios that may occur in very high temperature reactors (VHTRs). Phenomena identification and ranking studies to date have ranked an air ingress event, following on the heels of a VHTR depressurization, as important with regard to core safety. Consequently, the development of advanced air-ingress-related models and verification and validation data are a very high priority. Following a loss of coolant and system depressurization incident, air will enter the core of the High Temperature Gas Cooled Reactor through the break, possibly causing oxidation of the core and reflector graphite structure. Simple core and plant models indicate that, under certain circumstances, the oxidation may proceed at an elevated rate with additional heat generated from the oxidation reaction itself. Under postulated conditions of fluid flow and temperature, excessive degradation of lower plenum graphite can lead to a loss of structural support. Excessive oxidation of core graphite can also lead to a release of fission products into the confinement, which could be detrimental to reactor safety. Computational fluid dynamics models developed in this study will improve our understanding of this phenomenon. This paper presents two-dimensional (2-D) and three-dimensional (3-D) computational fluid dynamic (CFD) results for the quantitative assessment of the air ingress phenomena. A portion of the results from density-driven stratified flow in the inlet pipe will be compared with the experimental results.
Sponsorship	Heat Transfer Division
Starting Page	337
Ending Page	346
Page Count	10
File Format	PDF
ISBN	9780791849422
DOI	10.1115/IHTC14-23083
e-ISBN	9780791838792
Volume Number	2010 14th International Heat Transfer Conference, Volume 7
Conference Proceedings	2010 14th International Heat Transfer Conference
Language	English
Publisher Date	2010-08-08
Publisher Place	Washington, DC, USA
Access Restriction	Subscribed
Subject Keyword	Temperature Computational fluid dynamics Fluid dynamics High temperature Density Heat Very high temperature reactors Industrial research Graphite Coolants Gas cooled reactors Oxidation Safety Pipes Nuclear fission Stratified flow
Content Type	Text
Resource Type	Article

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