Thermal-hydraulic design of direct superheated steam blanket for the compact reversed shear tokamak reactor (CREST)

Y. Nomoto, T. Ishida, H. Ise, S. Mori, Y. Asaoka, T. Yoshida, R. Hiwatari, K. Okano

Research output: Contribution to journalArticle

2 Citations (Scopus)

Abstract

The compact reversed shear tokamak, CREST, is a cost competitive power reactor concept based on the reversed shear high beta plasma. As the cooling system of CREST blanket, the direct superheated steam cycle is adopted to simplify the heat transport/power generation system and to achieve high thermal efficiency with a water cooled concept. Thermal-hydraulic design of the blanket was performed for the nominal operation, the start-up operation and the partial load operation. As a result of the study, it was confirmed that the direct steam cycle blanket is promising for a power reactor and is feasible not only at the nominal operation condition but also at the reactor start-up and the partial load conditions.

Original languageEnglish
Pages (from-to)543-548
Number of pages6
JournalFusion Engineering and Design
Volume58-59
DOIs
Publication statusPublished - 2001 Nov 1

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Keywords

  • Blanket
  • CREST
  • Thermal-hydraulic
  • Tokamak

ASJC Scopus subject areas

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

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