Conceptual design of a breeding blanket with super-heated steam cycle for CREST-1

Yoshiyuki Asaoka, Kunihiko Okano, Tomoaki Yoshida, Ken Tomabechi, Yuichi Ogawa, Naoto Sekimura, Yuzo Fukai, Akiyoshi Hatayama, Nobuyuki Inoue, Akira Kohyama, Sei Ichiro Yamazaki, Seiji Mori

研究成果: Article査読

9 被引用数 (Scopus)

抄録

Compact REversed Shear Tokamak (CREST-1) is a conceptual design of water-cooled commercial reactor based on a reversed shear high beta equilibrium. The conceptual design of a tritium breeding blanket for CREST-1 is presented. This blanket design is based on low activation ferritic steel components and an advanced super-heated steam cycle. This design gives high thermal efficiency for the reduction of electricity cost. CREST-1 generates about 1.16 GWe electric power.

本文言語English
ページ(範囲)397-405
ページ数9
ジャーナルFusion Engineering and Design
48
3
DOI
出版ステータスPublished - 2000 9月

ASJC Scopus subject areas

  • 土木構造工学
  • 原子力エネルギーおよび原子力工学
  • 材料科学(全般)
  • 機械工学

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