Maintenance and radiation protection issues of the CREST reactor

Yoshiyuki Asaoka, Kunihiko Okano, Tomoaki Yoshida, Ken Tomabechi, Seiji Mori, Hideo Ise

研究成果: Conference article査読

3 被引用数 (Scopus)

抄録

A maintenance approach of the Compact Reversed Shear Tokamak (CREST) for high availability is proposed. Full sector removal through horizontal ports for easy maintenance is adopted in order to increase availability. Cask type sector removal machines are used to transfer the blanket/divertor sectors. Achievable availability is estimated with a maintenance period and its interval. The proposed maintenance approach allows, at least, the similar availability to that of the present nuclear plants. The estimated availability is acceptable from an economical viewpoint. Safety concerns related to the super-heated direct steam cycle are also examined. One of the unique concerns is due to nitrogen-16 production in the coolant. The super-heated steam must flow through the turbines within several 10 s after leaving the blanket. The requirements for shielding on the heat transfer systems are declared. Another concern is the confinement and recovery of tritium in the coolant, because a high temperature blanket may have a large tritium permeation rate. Water detritiation system proposed here would be able to control the tritium concentration in the coolant within an allowable range.

本文言語English
ページ(範囲)461-466
ページ数6
ジャーナルFusion Engineering and Design
51-52
DOI
出版ステータスPublished - 2000 11月
イベント5th Interantional Symposium on Fusion Technology - Rome, Italy
継続期間: 2000 9月 192000 9月 24

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
  • 材料科学一般
  • 機械工学

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