抄録
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.
本文言語 | 英語 |
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ページ | 525-532 |
ページ数 | 8 |
DOI | |
出版ステータス | 出版済み - 10月 19 2002 |
イベント | 10th International Conference on Nuclear Engineering (ICONE 10) - Arlington, VA, 米国 継続期間: 4月 14 2002 → 4月 18 2002 |
その他
その他 | 10th International Conference on Nuclear Engineering (ICONE 10) |
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国/地域 | 米国 |
City | Arlington, VA |
Period | 4/14/02 → 4/18/02 |
!!!All Science Journal Classification (ASJC) codes
- 原子力エネルギーおよび原子力工学