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, Kunihiko 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
Externally publishedYes

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Steam
Hydraulics
Cooling systems
Power generation
Plasmas
Water
Hot Temperature
Costs

Keywords

  • Blanket
  • CREST
  • Thermal-hydraulic
  • Tokamak

ASJC Scopus subject areas

  • Energy Engineering and Power Technology
  • Nuclear Energy and Engineering
  • Civil and Structural Engineering
  • Mechanical Engineering

Cite this

Thermal-hydraulic design of direct superheated steam blanket for the compact reversed shear tokamak reactor (CREST). / Nomoto, Y.; Ishida, T.; Ise, H.; Mori, S.; Asaoka, Y.; Yoshida, T.; Hiwatari, R.; Okano, Kunihiko.

In: Fusion Engineering and Design, Vol. 58-59, 11.2001, p. 543-548.

Research output: Contribution to journalArticle

Nomoto, Y. ; Ishida, T. ; Ise, H. ; Mori, S. ; Asaoka, Y. ; Yoshida, T. ; Hiwatari, R. ; Okano, Kunihiko. / Thermal-hydraulic design of direct superheated steam blanket for the compact reversed shear tokamak reactor (CREST). In: Fusion Engineering and Design. 2001 ; Vol. 58-59. pp. 543-548.
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