Two-phase pressure drop across abrupt area changes in oscillatory flow. [BWR and PWR]

Journal Article · Mon Nov 01 00:00:00 EST 1976 · Nucl. Sci. Eng.; (United States)

OSTI ID:7108339

Weisman, J; Ake, T; Knott, R

The ability of one-dimensional momentum balances to predict behavior during two-phase oscillatory flow has been examined. Flow oscillations in a Freon-Freon vapor system were induced by cycling a three-way valve so as to divert a varying portion of the total flow from the test section. The data taken included the phase shift between the pressure and flow curves and the head fluctuation to flow fluctuation ratio. These data were compared with theoretical predictions obtained via the impedance method. Although some discrepancies between predictions and measurements were observed, the discrepancies were generally within the range of error associated with the measurement and analysis techniques used.

• Research Organization: Univ. of Cincinnati
• OSTI ID: 7108339
• Journal Information: Nucl. Sci. Eng.; (United States), Vol. 61:3
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
LOSS OF COOLANT
HYDRAULICS
PRESSURE DROP
PWR TYPE REACTORS
LIQUID FLOW
ONE-DIMENSIONAL CALCULATIONS
REACTOR SAFETY
TEST FACILITIES
TWO-PHASE FLOW
ACCIDENTS
FLUID FLOW
FLUID MECHANICS
MECHANICS
REACTOR ACCIDENTS
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled