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 conferencePaper

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

Fingerprint

Cooling
Void fraction
Two phase flow
Heat flux
Liquids
Pressure vessels
Gases
Molten materials
Analytical models
Numerical methods
Hydraulics
Fluxes
Hot Temperature

All Science Journal Classification (ASJC) codes

  • Nuclear Energy and Engineering

Cite this

Uchibori, A., Fukuda, K., Morita, K., & Matsumoto, T. (2002). Numerical prediction of cooling capability in hemispherical gap flow passage for in-vessel core retention. 525-532. Paper presented at 10th International Conference on Nuclear Engineering (ICONE 10), Arlington, VA, United States. https://doi.org/10.1115/ICONE10-22334

Numerical prediction of cooling capability in hemispherical gap flow passage for in-vessel core retention. / Uchibori, Akihiro; Fukuda, Kenji; Morita, Koji; Matsumoto, Tatsuya.

2002. 525-532 Paper presented at 10th International Conference on Nuclear Engineering (ICONE 10), Arlington, VA, United States.

Research output: Contribution to conferencePaper

Uchibori, A, Fukuda, K, Morita, K & Matsumoto, T 2002, 'Numerical prediction of cooling capability in hemispherical gap flow passage for in-vessel core retention' Paper presented at 10th International Conference on Nuclear Engineering (ICONE 10), Arlington, VA, United States, 4/14/02 - 4/18/02, pp. 525-532. https://doi.org/10.1115/ICONE10-22334
Uchibori A, Fukuda K, Morita K, Matsumoto T. Numerical prediction of cooling capability in hemispherical gap flow passage for in-vessel core retention. 2002. Paper presented at 10th International Conference on Nuclear Engineering (ICONE 10), Arlington, VA, United States. https://doi.org/10.1115/ICONE10-22334
Uchibori, Akihiro ; Fukuda, Kenji ; Morita, Koji ; Matsumoto, Tatsuya. / Numerical prediction of cooling capability in hemispherical gap flow passage for in-vessel core retention. Paper presented at 10th International Conference on Nuclear Engineering (ICONE 10), Arlington, VA, United States.8 p.
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