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

Akihiro Uchibori, Kenji Fukuda, Koji Morita, Tatsuya Matsumoto

Research output: Contribution to conferencePaperpeer-review

2 Citations (Scopus)

Abstract

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.

Original languageEnglish
Pages525-532
Number of pages8
DOIs
Publication statusPublished - Oct 19 2002
Event10th International Conference on Nuclear Engineering (ICONE 10) - Arlington, VA, United States
Duration: Apr 14 2002Apr 18 2002

Other

Other10th International Conference on Nuclear Engineering (ICONE 10)
CountryUnited States
CityArlington, VA
Period4/14/024/18/02

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering

Fingerprint Dive into the research topics of 'Numerical prediction of cooling capability in hemispherical gap flow passage for in-vessel core retention'. Together they form a unique fingerprint.

Cite this