CFD investigation of vertical rod bundles of supercritical water-cooled nuclear reactor

  • Zhi Shang

Research output: Contribution to journalArticlepeer-review

Original languageEnglish
Pages (from-to)2562-2572
JournalNuclear Engineering and Design
Volume239
Issue number11
DOIs
Publication statusPublished - Nov 2009
Externally publishedYes

Keywords

  • heat-transfer
  • tube bundle
  • flows
  • design
  • model
  • Mechanical, aeronautical and manufacturing engineering

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