Assessment of a modified interfacial drag correlation in two-fluid model codes

Conference · Wed Dec 31 23:00:00 EST 1986 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:5627029

Hassan, Y A

Analysis of low flooding rate experiments and a number of boil-off experiments with the RELAP5/MOD2 computer code has shown that the code underpredicts the collapsed liquid level and, consequently, overpredicts the liquid carryover. Recent analyses using several other codes, e.g., TRAC-BD1 and the French code CATHARE, have also resulted in the underprediction of collapsed liquid level histories. The discrepancy between the measurements and code predictions is attributed to the interfacial drag between the phases. A new interfacial drag formulation in the bubbly/slug flow regimes is incorporated in the RELAP5/MOD2 code. Better agreement with the measurements is obtained.

• Research Organization: Texas A and M Univ., College Station
• OSTI ID: 5627029
• Report Number(s): CONF-870601-
• Journal Information: Trans. Am. Nucl. Soc.; (United States), Journal Name: Trans. Am. Nucl. Soc.; (United States) Vol. 54; ISSN TANSA
• Country of Publication: United States
• Language: English

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