TY - JOUR
T1 - Study on post-BT heat transfer in a full scale bwr (8 × 8) rod bundle
AU - Akiyama, Mamoru
AU - Inoue, Akira
AU - Ohishi, Masao
AU - Morooka, Shinichi
AU - Hoshide, Akehiko
AU - Ishizuka, Takao
AU - Yoshimura, Kunihiro
PY - 1989
Y1 - 1989
N2 - 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.
AB - 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.
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U2 - 10.1016/0029-5493(89)90183-0
DO - 10.1016/0029-5493(89)90183-0
M3 - Article
AN - SCOPUS:0010704623
SN - 0029-5493
VL - 117
SP - 341
EP - 347
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
IS - 3
ER -