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

Research output: Contribution to journalArticlepeer-review

9 Citations (Scopus)

Abstract

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.

Original languageEnglish
Pages (from-to)397-405
Number of pages9
JournalFusion Engineering and Design
Volume48
Issue number3
DOIs
Publication statusPublished - 2000 Sep

ASJC Scopus subject areas

  • Civil and Structural Engineering
  • Nuclear Energy and Engineering
  • Materials Science(all)
  • Mechanical Engineering

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