Graphite and Carbon Materials in Nuclear Engineering

Prof. Xu has worked in nuclear materials field since 1958, took part in building 2MW experimental shield reactor; R&D in nuclear fuel (UO2), graphite for liquid fuel reactors, BeO; in charge of R&D in HTR fuel technology (laboratory scale). Since 1993, Prof. Xu has interested in R&D of nuclear graphite and he has devoted to promote nuclear graphite development in China. Feiyu Kang received his PhD from The Hong Kong University of Science and Technology in 1997. He is honorary editorial advisory board of international journal CARBON, Joint Chairmen of international symposiums: CARBON2002 (Beijing), Carbon2011 (Shanghai) and 15th International Symposium on Intercalation Compounds (ISIC15), Coordinators of international research projects: Professor M. Inagaki (NSFC-JSPS) and Professor I. Mochida (JST-MOST).Prof. Kang has investigated graphite and carbon materials since 1988. His research interest includes nano-carbon materials, graphite producing process, porous carbon and nuclear graphite. Prof. Kang had published more than 200 scientific papers and 3 books. Prof. Tsang has more than 10 years experiences in nuclear graphite. Have been worked for Magnox nuclear reactor and Advanced Gas-cooled Reactor in United Kingdom and High Temperature Test Reactor (HTTR) in Japan. Now Prof. Tsang is working on the Thorium Molten Salt Reactor development in China. Prof. Tsang is committee members of ASME and ASTM.

1. Introduction
2. Basic knowledge of nuclear reactor
3. High temperature reactor
4. Molten salt reactor
5. Structure of carbonaceous materials
6. Production of nuclear graphite
7. Properties of nuclear graphite
8. Radiation effect of nuclear graphite
9. Decommissioning of nuclear graphite
10. Carbonaceous materials in fusion reactor