Studies of transition boiling heat transfer with saturated water at 1-4 bar. Final report

Technical Report · Mon Jun 01 04:00:00 EDT 1981

OSTI ID:6048800

Weisman, J; Kao, Y K; Wang, S; Pei, B

Steady-state and transient transition boiling heat transfer tests with water at low pressures have been conducted using a loop in which the test sections were heated by hot mercury. A revised heat transfer correlation was developed which provides a better fit of all the data. Transient heat transfer data in the transition boiling region were obtained in two separate test sections, in which the transient was initiated by a sudden increase of the water flow rate. Comparison indicates that the new heat transfer correlation also applies to transient data. The rewetting rates were dependent on local void fraction and test section geometry. At high void fractions in the annular test section, the rewetting rate was determined by the availability of cooling water to the heated surface. Phenomenological studies included void fraction measurement, visual and photographic observations and an examination of wall temperature fluctuations. In essentially all the experiments, the water was at the saturation temperature when transition boiling began.

• Research Organization: Cincinnati Univ., OH (USA). Dept. of Chemical and Nuclear Engineering
• OSTI ID: 6048800
• Report Number(s): EPRI-NP-1899; ON: DE81904219
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ANNULAR SPACE
BOILING
CONFIGURATION
CORE FLOODING SYSTEMS
CORRELATIONS
ECCS
ELEMENTS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
HEAT TRANSFER
LOSS OF COOLANT
MERCURY
METALS
PERFORMANCE
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTOR PROTECTION SYSTEMS
REACTORS
SPACE
STEADY-STATE CONDITIONS
TRANSIENTS
TUBES
VOID FRACTION
WATER COOLED REACTORS