Design and Construction of Special Pressure-Guide Tube for Measurement of ROSA-III Core Inlet Flow Rate

Shinichi Morooka, Osamu Kikuchi, Nobuhiko Inai, Hideo Murata, Kanji Tasaka

Research output: Contribution to journalArticle

Original languageEnglish
Pages (from-to)387-388
Number of pages2
JournalJournal of Nuclear Science and Technology
Volume18
Issue number5
DOIs
Publication statusPublished - 1981
Externally publishedYes

Keywords

  • BWR type reactors
  • cooling water
  • core inlet now rate
  • fuel assemblies
  • fuel cans
  • heat transfer
  • high pressure
  • high temperature
  • loss of coolant
  • pressure-guide tube
  • rig of safety assessment

ASJC Scopus subject areas

  • Nuclear and High Energy Physics
  • Nuclear Energy and Engineering

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