Survey of the literature applicable to two-phase natural circulation flows in the hot leg of a PWR: Final report

Technical Report · Wed Oct 01 00:00:00 EDT 1986

OSTI ID:7037602

Valenzuela, J A; Crowley, C J; Wallis, G B

This report reviews the two-phase flow literature relevant to the natural circulation flow in the hot leg of a pressurized water nuclear reactor during a small break loss of coolant accident. The phenomena of interest in two-phase naural circulation flows are numerous and complex. Three technical areas were identified for individual review in this report: gas-liquid flows in straight pipes; gas-liquid flows in bends; and two-phase natural circulation in reactor geometries. The literature has been surveyed, findings summarized, and suggestions have been made as to where the findings may influence thinking and model development for the reactor situation.

• Research Organization: Creare R and D, Inc., Hanover, NH (USA)
• OSTI ID: 7037602
• Report Number(s): EPRI-NP-4855; ON: TI87920133
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOSS OF COOLANT
HEAT TRANSFER
TWO-PHASE FLOW
PWR TYPE REACTORS
HYDRAULICS
MATHEMATICAL MODELS
NATURAL CONVECTION
PIPES
PRESSURE DROP
ACCIDENTS
CONVECTION
ENERGY TRANSFER
FLUID FLOW
FLUID MECHANICS
MASS TRANSFER
MECHANICS
REACTOR ACCIDENTS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled