2014
DOI: 10.1080/00223131.2013.877407
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CO2corrosion of IG-110 nuclear graphite studied by gas chromatography

Abstract: The CO 2 corrosion behavior of IG-110 nuclear graphite has been investigated using the gas chromatography method which allows the continuous analysis of the CO 2 /CO gas mixture at the outlet of the corrosion chamber. The effects of temperature and initial CO 2 concentration are studied based on the Arrhenius-type reaction model. From 745 to 995• C, the Arrhenius curve shows a linear behavior. For higher temperatures, a non-linear behavior is observed. The activation energy is calculated as 210 kJ/mole and is … Show more

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Cited by 13 publications
(2 citation statements)
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References 22 publications
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“…Consequently, the oxidation/corrosion of graphite arises to be a crucial issue to assess the economy and safety of a HTGR among which O 2 oxidation is usually the fastest reaction. There are two main concerned reactions related with O 2 oxidation of graphite when temperature is less than 900 °C 14 : The reaction ( 1 ) is considered as the intrinsic oxidation reaction between O 2 and graphite. Reaction ( 2 ) (CO combustion) may influence the reaction ( 1 ) (oxidation reaction) by varying O 2 supply and energy balance of reaction ( 1 ).…”
Section: Introductionmentioning
confidence: 99%
“…Consequently, the oxidation/corrosion of graphite arises to be a crucial issue to assess the economy and safety of a HTGR among which O 2 oxidation is usually the fastest reaction. There are two main concerned reactions related with O 2 oxidation of graphite when temperature is less than 900 °C 14 : The reaction ( 1 ) is considered as the intrinsic oxidation reaction between O 2 and graphite. Reaction ( 2 ) (CO combustion) may influence the reaction ( 1 ) (oxidation reaction) by varying O 2 supply and energy balance of reaction ( 1 ).…”
Section: Introductionmentioning
confidence: 99%
“…Samples of IG-110 and IG-430 graphite, also referred to as IG-11 and IG-43, were supplied by Toyo Tanso Ltd., Japan. IG-110 is a fine-grained, isotropic graphite which exhibits high thermal durability and strength, currently utilised in the Japanese high-temperature test reactor (HTTR) (Yan et al 2013) and the Chinese high-temperature reactor-pebble bed modules (HTR-10) (Zhen et al 2014). IG-430 is a comparable graphite, developed to display higher density, strength and thermal conductivity when compared with IG-110.…”
Section: Nuclear Graphitementioning
confidence: 99%