茨城講演会講演論文集
Online ISSN : 2424-2683
ISSN-L : 2424-2683
2019
会議情報

核融合炉用炭素系材料の機械的特性および微細組織に及ぼす中性子照射効果
*宇野 晃汰車田 亮伊藤 吾朗渥美 寿雄
著者情報
会議録・要旨集 認証あり

p. 408-

詳細
抄録

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.

著者関連情報
© 2019 一般社団法人 日本機械学会
前の記事 次の記事
feedback
Top