Development of a two-dimensional nuclear-thermal-coupled analysis code for conceptual blanket design of fusion reactors

Hiroyasu Utoh, Kenji Tobita, Youji Someya, Satoshi Sato, Yohji Seki, Haruhiko Takase

Research output: Contribution to journalArticle

11 Citations (Scopus)

Abstract

For conceptual blanket design of fusion reactors, a two-dimensional (2-D) nuclear-thermal-coupled analysis code, DOHEAT, has been developed. A remarkable feature of the code is a user-friendly graphical interface which allows to prepare an appropriate analysis model of a variety of blanket concepts with different materials in a short time. Furthermore, the code has a strong point that it provides the cross-sectional distribution of temperature, neutron/gamma fluxes, nuclear heating and tritium breeding ratio (TBR) inside the blanket after the completion of a single run. Throughout the DEMO design work in JAEA, it has proven that DOHEAT is extremely valuable in guiding the design study toward a wide variety of blanket concepts.

Original languageEnglish
Pages (from-to)2378-2381
Number of pages4
JournalFusion Engineering and Design
Volume86
Issue number9-11
DOIs
Publication statusPublished - 2011 Oct 1
Externally publishedYes

Keywords

  • Blanket
  • Design
  • DOT3.5
  • Fusion reactor
  • Nuclear analysis
  • Thermal analysis

ASJC Scopus subject areas

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

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