Analysis of stratified flow mixing
Conference
·
OSTI ID:5655925
The Creare 1/5-scale Phase II experiments which model fluid and thermal mixing of relatively cold high pressure injection (HPI) water into a cold leg of a full-scale pressurized water reactor (PWR) having loop flow are analyzed and found that they cannot achieve complete similarity with respect to characteristic Reynolds and Froude numbers and developing hydrodynamic entry length. Several analyses show that these experiments fall into two distinct regimes of mixing: momentum controlled and gravity controlled (stratification). 18 refs., 9 figs.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31-109-ENG-38
- OSTI ID:
- 5655925
- Report Number(s):
- CONF-850810-7; ON: DE85006840
- Resource Relation:
- Conference: National heat transfer conference, Denver, CO, USA, 4 Aug 1985
- Country of Publication:
- United States
- Language:
- English
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Analysis of stratified flow mixing
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OSTI ID:5655925
Transit time of mixed high pressure injection water and primary loop water in pressurized water reactor cold legs
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OSTI ID:5655925
COMMIX-1A analysis of fluid and thermal mixing in a model cold leg and downcomer of a PWR
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Sat Jan 01 00:00:00 EST 1983
·
OSTI ID:5655925
+3 more
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PRIMARY COOLANT CIRCUITS
THERMAL STRESSES
PWR TYPE REACTORS
HIGH PRESSURE COOLANT INJECTION
COMPUTERIZED SIMULATION
COOLING
FLUID FLOW
FROUDE NUMBER
HEAT TRANSFER
HYDRODYNAMICS
MOCKUP
REYNOLDS NUMBER
TRANSIENTS
COOLING SYSTEMS
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID MECHANICS
MECHANICS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTORS
SIMULATION
STRESSES
STRUCTURAL MODELS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
PRIMARY COOLANT CIRCUITS
THERMAL STRESSES
PWR TYPE REACTORS
HIGH PRESSURE COOLANT INJECTION
COMPUTERIZED SIMULATION
COOLING
FLUID FLOW
FROUDE NUMBER
HEAT TRANSFER
HYDRODYNAMICS
MOCKUP
REYNOLDS NUMBER
TRANSIENTS
COOLING SYSTEMS
ECCS
ENERGY SYSTEMS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
FLUID MECHANICS
MECHANICS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR PROTECTION SYSTEMS
REACTORS
SIMULATION
STRESSES
STRUCTURAL MODELS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210200 - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled