Numerical prediction of cooling capability in hemispherical gap flow passage for in-vessel core retention

Akihiro Uchibori, Kenji Fukuda, Koji Morita, Tatsuya Matsumoto

研究成果: Contribution to conferencePaper査読

2 被引用数 (Scopus)

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
ページ525-532
ページ数8
DOI
出版ステータス出版済み - 10 19 2002
イベント10th International Conference on Nuclear Engineering (ICONE 10) - Arlington, VA, 米国
継続期間: 4 14 20024 18 2002

その他

その他10th International Conference on Nuclear Engineering (ICONE 10)
国/地域米国
CityArlington, VA
Period4/14/024/18/02

All Science Journal Classification (ASJC) codes

  • 原子力エネルギーおよび原子力工学

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