In the high temperature gas-cooled reactor, the oxidation of graphite is inevitable as a result of impurities in helium coolant. As an air or water ingress accident would cause graphite components to oxidize more seriously, thereby it would affect the reactor normal operation and safety. Oxidation velocity and oxidation product of a selected graphite (excess material from 10MW High Temperature Gas-cooled Reactor) were studied, samples are oxidized between 400°C to 1200 °C with gas flow rates ranging from 125 to 500 ml/min. Relationship between oxidation conditions and surface properties of oxidized graphite is also elaborated by means of gas chromatography and scanning electron microscopy for scanning of graphite surface.
- Nuclear Engineering Division
Experimental Study on Oxidation of Graphite for HTR
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Liu, Y, Sun, X, & Dong, Y. "Experimental Study on Oxidation of Graphite for HTR." Proceedings of the 2013 21st International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications. Chengdu, China. July 29–August 2, 2013. V001T02A024. ASME. https://doi.org/10.1115/ICONE21-15808
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