Kinematics of two-phase mixture level motion in BWR pressure vessels

Conference · Tue Jan 01 00:00:00 EST 1985

OSTI ID:5715972

Wulff, W; Cheng, H S; Mallen, A N; Stritar, A

A model is presented for predicting two-phase mixture level elevations in BWR systems. The model accounts for the particular geometry and conditions in a BWR system during Small-Break Loss of Coolant Accidents. The model presented here is particularly suitable for efficient, high-speed simulations on small minicomputers. The model has been implemented and tested. Results are shown from BWR ATWS simulations.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 5715972
• Report Number(s): BNL-NUREG-36474; CONF-850646-4; ON: TI85013292
• Resource Relation: Conference: 2. international specialists meeting on small break LOCA analysis in LWRs, Pisa, Italy, 24 Jun 1985
• 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
PRESSURE VESSELS
TWO-PHASE FLOW
ATWS
HYDRAULICS
PRIMARY COOLANT CIRCUITS
ACCIDENTS
CONTAINERS
COOLING SYSTEMS
ENERGY SYSTEMS
FLUID FLOW
FLUID MECHANICS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled