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The oxidation effects of nuclear graphite during air-ingress accidents in HTGR
 

The oxidation effects of nuclear graphite during air-ingress accidents in HTGR

Wei-Hao Huang, Shuo-Cheng Tsai, I-Che Chiu, Chien-Hung Chen Ji-Jung Kai
Nuclear Engineering and Design, Vol.271, pp.270-274
2014
: https://doi.org/10.1016/j.nucengdes.2013.11.047
: WOS:000336348100045
Nuclear Energy and Engineering Risk Reliability and Quality Materials Science (all) Nuclear and High Energy Physics Waste Management and Disposal Mechanical Engineering Safety
This study consists of two main parts. The first part presents an experimental investigation of two types of nuclear graphite (IG-110, IG-430) at temperatures ranging from 700 to 1000 °C. Mercury porosimetry results and the quantification of pores in SEM/OM image show that the pores (pore diameter >4 μm) tended to grow into larger pores at temperatures >700 °C. The second part of this study presents a simulation of air-ingress accident. This experiment was conducted at temperatures ranging from 800 to 1000 °C with a flow rate of 0.35 L/min to simulate an air-ingress accident. Results indicate that IG-430 showed a tremendous improvement over IG-110 at medium temperature (<800 °C). However, the advantages of IG-430 began to diminish when the temperature increased. © 2013 Elsevier B.V.
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7 Engineering & Materials Science
7.139 Energy & Fuels
7.139.1825 Carbon Materials
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Nuclear Science & Technology
esploro.research.conf.research.portal.label.prefix.inciteESIResearchAreas
Engineering
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