TY - GEN
T1 - R&D and irradiation plans for new nuclear grade graphites for application to VHTR
AU - Takizawa, Kentaro
AU - Kakehashi, Kazuyuki
AU - Fukuda, Toshiaki
AU - Kida, Tohru
AU - Sawa, Kazuhiro
AU - Sumita, Junya
AU - Katoh, Yutai
AU - Snead, Lance L.
PY - 2011
Y1 - 2011
N2 - Fine-grained isotropic graphite shows high strength making it a promising material for the graphite component of High Temperature Gas-cooled Reactor (HTGR) and Very High Temperature Reactor (VHTR). Service life of the graphite component is determined primarily by the residual stress after neutron irradiation in the reactor core. It is expected that development of new fine-grained isotropic nuclear grade graphite possessing higher strength will contribute toward added design margins and an extension of the service life of components, which likely improve the reactor economy very significantly. Tokai Carbon Co. LTD. has started the development of nuclear grade graphite having high strength for the graphite component of VHTR. As the start of evaluation to the application for VHTR, the evaluation based on Japanese draft standard for HTGR is advanced. Japanese draft standard demands as follows, (1)Guarantee a stable supply for long period, (2)Obtain the data for design, (3)Confirms stable features under high temperature and irradiation condition. The following conclusions were obtained. (1)To satisfy the requirement of stable supply, G347S and G458S grades was selected. These products showed excellent properties. (2)Obtaining the data is still on the way. However some obtained data showed excellent value. (3)It is planned to carry out the neutron irradiation tests using High Flux Isotope Reactor at Oak Ridge National Laboratory up to the neutron fluence of 30 dpa, and the irradiation temperatures of 300-900°C. It is scheduled to end in 2014. The dimensional changes, elastic modulus, coefficient of thermal expansion, etc., will be studied.
AB - Fine-grained isotropic graphite shows high strength making it a promising material for the graphite component of High Temperature Gas-cooled Reactor (HTGR) and Very High Temperature Reactor (VHTR). Service life of the graphite component is determined primarily by the residual stress after neutron irradiation in the reactor core. It is expected that development of new fine-grained isotropic nuclear grade graphite possessing higher strength will contribute toward added design margins and an extension of the service life of components, which likely improve the reactor economy very significantly. Tokai Carbon Co. LTD. has started the development of nuclear grade graphite having high strength for the graphite component of VHTR. As the start of evaluation to the application for VHTR, the evaluation based on Japanese draft standard for HTGR is advanced. Japanese draft standard demands as follows, (1)Guarantee a stable supply for long period, (2)Obtain the data for design, (3)Confirms stable features under high temperature and irradiation condition. The following conclusions were obtained. (1)To satisfy the requirement of stable supply, G347S and G458S grades was selected. These products showed excellent properties. (2)Obtaining the data is still on the way. However some obtained data showed excellent value. (3)It is planned to carry out the neutron irradiation tests using High Flux Isotope Reactor at Oak Ridge National Laboratory up to the neutron fluence of 30 dpa, and the irradiation temperatures of 300-900°C. It is scheduled to end in 2014. The dimensional changes, elastic modulus, coefficient of thermal expansion, etc., will be studied.
UR - http://www.scopus.com/inward/record.url?scp=80155174304&partnerID=8YFLogxK
U2 - 10.1002/9781118095386.ch2
DO - 10.1002/9781118095386.ch2
M3 - Conference contribution
AN - SCOPUS:80155174304
SN - 9781118059944
T3 - Ceramic Engineering and Science Proceedings
SP - 13
EP - 19
BT - Ceramic Materials for Energy Applications - A Collection of Papers Presented at the 35th International Conference on Advanced Ceramics and Composites, ICACC
PB - American Ceramic Society
T2 - Ceramic Materials for Energy Applications - 35th International Conference on Advanced Ceramics and Composites, ICACC
Y2 - 23 January 2011 through 28 January 2011
ER -