Structure of Carbon-Coated Graphite and its Application in Nuclear Industry

Abstract:

High Temperature Gas-cooled Reactor is one of the candidates for the next generation advanced nuclear energy systems. As high temperature gas cooled reactor neutron moderator, reflector and structural material, nuclear graphite is very important in the nuclear industry to assure the safe operation of the reactor. The oxide reactor of nuclear graphite will change its internal pore structure and properties, such as mechanics properties, thermodynamic performance, radiant resistance, and so on. In this study, graphite coated with carbon was prepared by liquid impregnation method. Infrared spectral radiometry (FTIR), scanning electron microscope (SEM) and thermal gravity analysis (TGA) methods were used to characterize the structure of the carbon-coated graphite. Neutron absorption test method was also used to test the resistance to radiation. The results show that when the heat treatment time was 6h with the heat treatment temperature was 500¡æ, the material had the best morphology and had the largest neutron adsorption area (4.63 mb). The results suggest that this carbon-coated graphite has very good application prospect in nuclear industry.

• Periodical: Advanced Materials Research (Volume 952)
• Pages: 100-104
• DOI: https://doi.org/10.4028/www.scientific.net/AMR.952.100
• Online since: May 2014
• Authors: Wan Li Xing, An Jian Wang, Qi Shen Chen*
• Keywords: Carbon-Coated, Liquid Impregnation Method, Nuclear Graphite , Nuclear Industry, Oxidation

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