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

研究成果: Article査読

5 被引用数 (Scopus)

抄録

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.

本文言語English
ページ(範囲)341-347
ページ数7
ジャーナルNuclear Engineering and Design
117
3
DOI
出版ステータスPublished - 1989
外部発表はい

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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