A numerical method for thermal hydraulic phenomena in a hemispherical narrow gap flow passage was developed to evaluate a cooling capability with gap formation between the molten core and the reactor pressure vessel.The gap cooling mechanism was modeled as gas-liquid two-phase flow in the narrow gap with two-dimensional spherical coordinate system. The analytical model is based on a modified drift flux model for multi-dimensional two-phase flow analysis. Numerical results showed that liquid phase intrusion into the gap in the counter direction of gas phase upward flow kept down a rise of void fraction as gap cooling phenomena. Under the high heat flux condition,expansion of the high void fraction region due to the counter-current flow limitation was reproduced as a dryout phenomenon. Characteristics of gap cooling limitation predicted by the numerical analyses were verified by comparison with various experimental data and correlations of critical heat flux.
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10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3597-9
PROCEEDINGS PAPER
Numerical Prediction of Cooling Capability in Hemispherical Gap Flow Passage for In-Vessel Core Retention Available to Purchase
Akihiro Uchibori,
Akihiro Uchibori
Kyushu University, Fukuoka, Japan
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Kenji Fukuda,
Kenji Fukuda
Kyushu University, Fukuoka, Japan
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Koji Morita,
Koji Morita
Kyushu University, Fukuoka, Japan
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Tatsuya Matsumoto
Tatsuya Matsumoto
Kyushu University, Fukuoka, Japan
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Akihiro Uchibori
Kyushu University, Fukuoka, Japan
Kenji Fukuda
Kyushu University, Fukuoka, Japan
Koji Morita
Kyushu University, Fukuoka, Japan
Tatsuya Matsumoto
Kyushu University, Fukuoka, Japan
Paper No:
ICONE10-22334, pp. 525-532; 8 pages
Published Online:
March 4, 2009
Citation
Uchibori, A, Fukuda, K, Morita, K, & Matsumoto, T. "Numerical Prediction of Cooling Capability in Hemispherical Gap Flow Passage for In-Vessel Core Retention." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 14–18, 2002. pp. 525-532. ASME. https://doi.org/10.1115/ICONE10-22334
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