Columbia University flow instability experimental program: Volume 3. Single tube parallel flow tests
The coolant in the Savannah River Site (SRS) production nuclear reactor assemblies is circulated as a subcooled liquid under normal operating conditions. This coolant is evenly distributed throughout multiple annular flow channels with a uniform pressure profile across each coolant flow channel. During the postulated Loss of Coolant Accident (LOCA), which is initiated by a hypothetical guillotine pipe break, the coolant flow through the reactor assemblies is significantly reduced. The flow reduction and accompanying power reduction (after shutdown is initiated) occur in the first 1--2 seconds of the LOCA. This portion of the LOCA is referred to as the Flow Instability phase. A series of down flow experiments have been conducted on three different size single tubes. The objective of these experiments was to determine the effect of a parallel flow path on the occurrence of flow instability. In all cases, it has been shown that the point of flow instability (OFI) determined under controlled flow operation does not change when operating in a controlled pressure drop mode (parallel path operation).
- Research Organization:
- Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Organization:
- USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC09-89SR18035
- OSTI ID:
- 10168371
- Report Number(s):
- WSRC-TR--93-684; ON: DE94015496
- Country of Publication:
- United States
- Language:
- English
Similar Records
Columbia University flow instability experimental program: Volume 6. Single annulus tests, transient test program
Modeling the onset of flow instability for subcooled boiling in downflow
Design inputs document: Boiling behavior during flow instability
Technical Report
·
Tue Sep 01 00:00:00 EDT 1992
·
OSTI ID:10168364
Modeling the onset of flow instability for subcooled boiling in downflow
Conference
·
Sun Dec 31 23:00:00 EST 1989
·
OSTI ID:6397988
Design inputs document: Boiling behavior during flow instability
Technical Report
·
Mon Dec 31 23:00:00 EST 1990
·
OSTI ID:5630982
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600
220900
ACCURACY
DATA ACQUISITION SYSTEMS
EXPERIMENTAL DATA
FLOW RATE
FUEL ASSEMBLIES
FUEL CHANNELS
LOSS OF COOLANT
MEASURING INSTRUMENTS
PRESSURE MEASUREMENT
REACTOR SAFETY
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
SAVANNAH RIVER PLANT
SPECIAL PRODUCTION REACTORS
TEMPERATURE MEASUREMENT
TEST FACILITIES
UNSTEADY FLOW
220600
220900
ACCURACY
DATA ACQUISITION SYSTEMS
EXPERIMENTAL DATA
FLOW RATE
FUEL ASSEMBLIES
FUEL CHANNELS
LOSS OF COOLANT
MEASURING INSTRUMENTS
PRESSURE MEASUREMENT
REACTOR SAFETY
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
SAVANNAH RIVER PLANT
SPECIAL PRODUCTION REACTORS
TEMPERATURE MEASUREMENT
TEST FACILITIES
UNSTEADY FLOW