Study on post-BT heat transfer in a full scale bwr (8 × 8) rod bundle

Mamoru Akiyama, Akira Inoue, Masao Ohishi, Shinichi Morooka, Akehiko Hoshide, Takao Ishizuka, Kunihiro Yoshimura

Research output: Contribution to journalArticle

5 Citations (Scopus)

Abstract

Post-BT heat transfer experiments on a full scale BWR (8 × 8) rod bundle were conducted at the Nuclear Power Engineering Test Center (NUPEC), which is sponsored by the Ministry of International Trade and Industry (MITI). Demineralized water was used as a test fluid. The experimental conditions were: Mass flux: 284 to 1562 kg/m2s, Pressure: 7.15 MPa, Inlet subcooling: 50 kJ/kg. Test results indicate that the rod temperature rise after boiling transition (BT) is not "excursive". Comparisons with several existing post-BT correlations indicate that the Groeneveld, The Dougall-Rohsenow and the Condie-Bengston correlations tend to be conservative in the intermediate range before the onset of fully developed film boiling, while the Koizumi and the Sugawara correlations predict well over the complete Post-BT range.

Original languageEnglish
Pages (from-to)341-347
Number of pages7
JournalNuclear Engineering and Design
Volume117
Issue number3
DOIs
Publication statusPublished - 1989
Externally publishedYes

ASJC Scopus subject areas

  • Energy Engineering and Power Technology
  • Nuclear Energy and Engineering
  • Civil and Structural Engineering
  • Mechanical Engineering
  • Safety, Risk, Reliability and Quality

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  • Cite this

    Akiyama, M., Inoue, A., Ohishi, M., Morooka, S., Hoshide, A., Ishizuka, T., & Yoshimura, K. (1989). Study on post-BT heat transfer in a full scale bwr (8 × 8) rod bundle. Nuclear Engineering and Design, 117(3), 341-347. https://doi.org/10.1016/0029-5493(89)90183-0