Pressure Drop of Tight Lattice Rod Bundle

Shinichi Morooka, Yasushi Yamamoto, Kenetsu Shirakawa

研究成果: Article

8 引用 (Scopus)

抄録

The fuel assembly design with tightened fuel rod pitch gives a possibility of higher conversion ratio for Boiling Water Reactor (s). Pressure drop is one of the key design parameters to evaluate the possibility of BWR core with higher conversion ratio. The pressure drop test for tight lattice rod bundles under steady conditions has been done under BWR fluid conditions. The following results were obtained: (1) The present prediction method has the reasonable performance under 25% of quality at the rated mass flux, but the predicted value is larger than the measured ones for larger mass flux.(2) This method can be applied to evaluate the pressure drop for tight lattice bundles from the conservative point of view, but it is necessary to improve the predicted accuracy for larger mass flux.

元の言語English
ページ(範囲)301-306
ページ数6
ジャーナルTransactions of the Atomic Energy Society of Japan
2
発行部数3
DOI
出版物ステータスPublished - 2003
外部発表Yes

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Pressure drop
Mass transfer
Boiling water reactors
Fluids

ASJC Scopus subject areas

  • Nuclear Energy and Engineering
  • Safety, Risk, Reliability and Quality

これを引用

Pressure Drop of Tight Lattice Rod Bundle. / Morooka, Shinichi; Yamamoto, Yasushi; Shirakawa, Kenetsu.

:: Transactions of the Atomic Energy Society of Japan, 巻 2, 番号 3, 2003, p. 301-306.

研究成果: Article

Morooka, Shinichi ; Yamamoto, Yasushi ; Shirakawa, Kenetsu. / Pressure Drop of Tight Lattice Rod Bundle. :: Transactions of the Atomic Energy Society of Japan. 2003 ; 巻 2, 番号 3. pp. 301-306.
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