Thermal oscillations downstream of an elbow in stratified pipe flow
Conference
·
OSTI ID:6837075
In previously published papers, the test geometry, test methodology and the scope of the thermal transient induced pipe stratification studies at Argonne National Laboratory (ANL) were explained. In these prior studies, limited fluid temperature data from elbow inlet and exit plane thermocouples indicated the presence of large-amplitude thermal fluctuations for conditions in which the horizontal pipe upstream of the elbow developed stratified flow induced by a pipe entrant thermal transient. Under severe transient conditions, thermal oscillations of amplitude of almost 70 percent of the pipe inlet transient temperature change were observed in the bulk flow. TC data and accompanying flow visualization test results showed that the largest near wall thermal oscillations were located within and immediately downstream of the elbow. The thermal oscillations if they are of large enough amplitude, of the appropriate frequency, and of sufficiently long duration can cause thermal stripping and thermal-fatigue stress cracking in the elbow region. A specially instrumented test section was fabricated to study these thermal fluctuations.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6837075
- Report Number(s):
- CONF-840614-27; ON: DE84006550
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MECHANICS
OSCILLATIONS
PIPES
POWER REACTORS
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE GRADIENTS
TEST FACILITIES
TRANSIENTS
220900* -- Nuclear Reactor Technology-- Reactor Safety
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
MECHANICS
OSCILLATIONS
PIPES
POWER REACTORS
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
SAFETY
TEMPERATURE GRADIENTS
TEST FACILITIES
TRANSIENTS