Two-phase flow regimes in a large-diameter model of a PWR hot leg

Conference · Fri Nov 01 04:00:00 EST 1985 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:5691793

Hashemi, A; Kim, J H; Sursock, J P

Knowledge of flow regimes in the hot legs and the steam generators of a pressurized water reactor (PWR) is essential in understanding and predicting the overall system thermal-hydraulic response during a small-break loss-of-coolant accident (SBLOCA). Flow regime characterization becomes especially important when natural circulation conditions prevail (low flow rates and high quality) and the potential for breakdown in flow is enhanced. To characterize flow regimes in PWR hot leg geometry, an experimental investigation with 10.2-cm diam glass pipe was carried out. These results showed that valuable information can be obtained from atmospheric pressure air-water flow tests in reactor geometries. This paper describes some preliminary results of 30.5-cm pipe tests.

• Research Organization: Science Applications International Corp., Los Altos, CA
• OSTI ID: 5691793
• Report Number(s): CONF-851115-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 50
• Country of Publication: United States
• Language: English

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ACCIDENTS
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PIPES
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REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
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STEAM GENERATORS
TWO-PHASE FLOW
VAPOR GENERATORS
VOID FRACTION
WATER COOLED REACTORS
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