主催: 一般社団法人日本機械学会
会議名: 第27回茨城講演会
開催日: 2019/08/22
p. 408-
The divertor materials, which receive the highest heat flux load in the next large nuclear fusion experimental devices are considered to use carbon fiber reinforced carbon composites (C/C composites) and tungsten material. C/C composites have the highest heat resistance (sublimation at 3,650K) and the highest thermal shock resistance in materials, and are considered to be the only material which can bear up against the highest heat flux load such as a plasma disruption. In this research, an isotropic graphite, a pyrolytic graphite and a C/C composite were irradiated by neutron with a low temperature and a high neutron flux in the research reactor (BR2) of Belgium. The fundamental knowledges about the neutron irradiation effects on mechanical properties and microstructures of carbon materials were obtained.