Experimental study on the oxidation of nuclear graphite and development of an oxidation model

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The present study investigates the graphite oxidation, which is one of the most serious problems during an air-ingress accident of a high temperature gas-cooled reactor (HTGR). In our study, oxidation experiments have been performed for IG-110 graphite by gas analysis under the various temperatures and oxygen concentrations. As a result, the order of reaction (n) and activation energy (E-a) were estimated as 0.75 +/- 0.146 and 218 +/- 3.76 kJ/mol, respectively within a 95% confidence level. The CO/CO2 ratios were also measured and compared with Aurthur's and Rossberg's correlations. Most of data lie between their predictions, but for better prediction.. an empirical correlation was newly developed. We measured reaction rates and analyzed them with a computational fluid dynamics (CFD) simulation by incorporating the oxidation parameters and the CO/CO2 ratio estimated here. Finally, an analytical model that includes both the chemical reaction and mass transfer was proposed and validated against experimental data. (c) 2005 Elsevier B.V. All rights reserved.
Publisher
ELSEVIER SCIENCE BV
Issue Date
2006-02
Language
English
Article Type
Article
Keywords

GRADE GRAPHITES; FLOW

Citation

JOURNAL OF NUCLEAR MATERIALS, v.349, no.1-2, pp.182 - 194

ISSN
0022-3115
DOI
10.1016/j.jnucmat.2005.10.015
URI
http://hdl.handle.net/10203/90000
Appears in Collection
NE-Journal Papers(저널논문)
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