Flow recirculation data for closed-ended branch piping (deep cavity flow)
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:5490120
- Westinghouse Electric Corporation, Madison, PA (USA)
Many auxiliary lines of different sizes are tied into the primary heat transport system piping of nuclear reactors and other similar types of systems. Often these lines are valve closed so that the contained fluid is either stagnant or flowing at low velocity due to free convection or small amounts of valve leakage. The characterization of the axial temperature distributions in these lines is important because of potential structural consequences to the piping. For example, in addition to being required for determining basic thermal expansion allowances in piping networks, axial temperature distributions are needed relative to other considerations, such as thermal fatigue, which could occur because the leakage flow has a different temperature from that of the trunk line that it flows into at the juncture of the two pipes. As would be anticipated, conditions that result in larger fluid temperature differences at a particular network juncture generally result in the more severe structural impact (e.g., thermal stratification/striping assessments become necessary). Prediction of the flow recirculation back into the branch piping is critical for calculation of the junction temperatures and is the subject of this study.
- OSTI ID:
- 5490120
- Report Number(s):
- CONF-891103--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 60
- Country of Publication:
- United States
- Language:
- English
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Conference
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Sat Dec 31 23:00:00 EST 1988
· Transactions of the American Nuclear Society; (USA)
·
OSTI ID:6852607
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Conference
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Conference
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200* -- Nuclear Reactor Technology-- Components & Accessories
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
CHLORINATED ALIPHATIC HYDROCARBONS
CLOSED CONFIGURATIONS
COMPUTERIZED SIMULATION
COOLING SYSTEMS
DATA
DESIGN
ENERGY SYSTEMS
EXPERIMENTAL DATA
FATIGUE
FLOW MODELS
FLUID MECHANICS
HALOGENATED ALIPHATIC HYDROCARBONS
HYDRAULICS
INFORMATION
MAGNETIC FIELD CONFIGURATIONS
MATHEMATICAL MODELS
MECHANICAL PROPERTIES
MECHANICS
MIXING
NUMERICAL DATA
ORGANIC CHLORINE COMPOUNDS
ORGANIC COMPOUNDS
ORGANIC HALOGEN COMPOUNDS
ORGANIC POLYMERS
PIPES
POLYMERS
POLYVINYLS
PVC
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
SIMULATION
STRATIFICATION
THERMAL FATIGUE
220200* -- Nuclear Reactor Technology-- Components & Accessories
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
CHLORINATED ALIPHATIC HYDROCARBONS
CLOSED CONFIGURATIONS
COMPUTERIZED SIMULATION
COOLING SYSTEMS
DATA
DESIGN
ENERGY SYSTEMS
EXPERIMENTAL DATA
FATIGUE
FLOW MODELS
FLUID MECHANICS
HALOGENATED ALIPHATIC HYDROCARBONS
HYDRAULICS
INFORMATION
MAGNETIC FIELD CONFIGURATIONS
MATHEMATICAL MODELS
MECHANICAL PROPERTIES
MECHANICS
MIXING
NUMERICAL DATA
ORGANIC CHLORINE COMPOUNDS
ORGANIC COMPOUNDS
ORGANIC HALOGEN COMPOUNDS
ORGANIC POLYMERS
PIPES
POLYMERS
POLYVINYLS
PVC
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
SIMULATION
STRATIFICATION
THERMAL FATIGUE