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

Fingerprint

loss of coolant
inlet flow
Inlet flow
liquid cooling
Cooling water
flow velocity
heat transfer
Flow rate
tubes
Heat transfer

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

Cite this

Design and Construction of Special Pressure-Guide Tube for Measurement of ROSA-III Core Inlet Flow Rate. / Morooka, Shinichi; Kikuchi, Osamu; Inai, Nobuhiko; Murata, Hideo; Tasaka, Kanji.

In: Journal of Nuclear Science and Technology, Vol. 18, No. 5, 1981, p. 387-388.

Research output: Contribution to journalArticle

Morooka, Shinichi ; Kikuchi, Osamu ; Inai, Nobuhiko ; Murata, Hideo ; Tasaka, Kanji. / Design and Construction of Special Pressure-Guide Tube for Measurement of ROSA-III Core Inlet Flow Rate. In: Journal of Nuclear Science and Technology. 1981 ; Vol. 18, No. 5. pp. 387-388.
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AU - Tasaka, Kanji

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KW - rig of safety assessment

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