著者

山内 通則 西谷 健夫 西尾 敏

出版者

社団法人 プラズマ・核融合学会

雑誌

プラズマ・核融合学会誌 (ISSN:09187928)

巻号頁・発行日

vol.80, no.11, pp.952-954, 2004 (Released:2005-07-14)

参考文献数

2

---

Considering the geometrical characteristics of tokamak reactors with low aspect ratio, a basic neutronics strategy was derived to construct an inboard structure mainly for neutron shielding and to produce enough tritium in the outboard blanket. The designs for optimal inboard shield were surveyed and the necessary thickness was estimated to make the neutron flux sufficiently low on the super-conducting magnet. In addition, the outer blanket designs were studied to attain a tritium breeding ratio (TBR) sufficiently large for a self-sustaining fusion reactor on the basis of advanced fusion reactor materials.