Nuclear graphite for high temperature gas-cooled reactors

ZHOU Xiang-wen; TANG Ya-ping; LU Zhen-ming; ZHANG Jie; LIU Bing

doi:10.1016/S1872-5805(17)60116-1

Volume 32 Issue 3

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Article Navigation > New Carbon Mater. > 2017 > 32(3): 193-204

ZHOU Xiang-wen, TANG Ya-ping, LU Zhen-ming, ZHANG Jie, LIU Bing. Nuclear graphite for high temperature gas-cooled reactors. New Carbon Mater., 2017, 32(3): 193-204. doi: 10.1016/S1872-5805(17)60116-1

Citation:

ZHOU Xiang-wen, TANG Ya-ping, LU Zhen-ming, ZHANG Jie, LIU Bing. Nuclear graphite for high temperature gas-cooled reactors. New Carbon Mater., 2017, 32(3): 193-204. doi: 10.1016/S1872-5805(17)60116-1

ZHOU Xiang-wen, TANG Ya-ping, LU Zhen-ming, ZHANG Jie, LIU Bing. Nuclear graphite for high temperature gas-cooled reactors. New Carbon Mater., 2017, 32(3): 193-204. doi: 10.1016/S1872-5805(17)60116-1

Citation:

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Nuclear graphite for high temperature gas-cooled reactors

doi: 10.1016/S1872-5805(17)60116-1

Institute of Nuclear and New Energy Technology of Tsinghua University, Collaborative Innovation Center of Advanced Nuclear Energy Technology, the key laboratory of advanced reactor engineering and safety, Ministry of Education, Beijing 100084, China

Funds: State Scholarship Foundation of China (201406215002);Chinese National S&T Major Project (ZX06901);Tsinghua University Initiative Scientific Research Program (20121088038).

Received Date: 2017-02-26
Accepted Date: 2017-06-28
Rev Recd Date: 2017-05-13
Publish Date: 2017-06-28

Abstract

Abstract

Since its first successful use in the CP-1 nuclear reactor in 1942,nuclear graphite has played an important role in nuclear reactors especially the high temperature gas-cooled type (HTGRs) owing to its outstanding comprehensive nuclear properties.As the most promising candidate for generation IV reactors,HTGRs have two main designs,the pebble bed reactor and the prismatic reactor.In both designs,the graphite acts as the moderator,fuel matrix,and a major core structural component.However,the mechanical and thermal properties of graphite are generally reduced by the high fluences of neutron irradiation of during reactor operation,making graphite more susceptible to failure after a significant neutron dose.Since the starting raw materials such as the cokes and the subsequent forming method play a critical role in determining the structure and corresponding properties and performance of graphite under irradiation,the judicious selection of high-purity raw materials,forming method,graphitization temperature and any halogen purification are required to obtain the desired properties such as the purity and isotropy.The microstructural and corresponding dimensional changes under irradiation are the underlying mechanism for the changes of most thermal and mechanical properties of graphite,and irradiation temperature and neutron fluence play key roles in determining the microstructural and property changes of the graphite.In this paper,the basic requirements of nuclear graphite as a moderator for HTGRs and its manufacturing process are presented.In addition,changes in the mechanical and thermal properties of graphite at different temperatures and under different neutron fluences are elaborated.Furthermore,the current status of nuclear graphite development in China and abroad is discussed,and long-term problems regarding nuclear graphite such as the sustainable and stable supply of cokes as well as the recycling of used material are discussed.This paper is intended to act as a reference for graphite providers who are interested in developing nuclear graphite for potential applications in future commercial Chinese HTGRs.
- Nuclear graphite,
- High temperature gas-cooled reactors,
- Irradiation,
- Microstructure,
- Physical,mechanical and thermal properties

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References(24)

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