CANDU-600 heat transport system flow stability
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:6744593
The thermohydraulic stability of the Canada deuterium uranium (CANDU)-600 heat transport system was investigated from a theoretical, numerical, and experimental point of view. Simple theoretical models, used to provide phenomenological insight as a guide to the numerical and experimental studies, showed that a major form of positive feedback existed through an interplay of circuit flow, outlet header void fraction, and outlet header pressure. The flow and pressure dynamics proved to be good indicators of system stability. System computer codes (SOPHT, FIREBIRD, and HYDNA) were used for the detailed modeling of system dynamics. These codes showed that neither Ledinegg nor parallel channel instabilities occur in CANDU-600 nuclear reactors. Loop stability was predicted under all conditions with the reactor outlet header interconnect line in service as designed. With the interconnect line disconnected, loop instability was predicted for a narrow outlet header quality range ( 1 to 8%). These predictions were fully confirmed by semiscale experimental loop tests and plant commissioning tests.
- Research Organization:
- Dept. of Engineering Physics, Hamilton, Ontario L8S 4M1
- OSTI ID:
- 6744593
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 75:3; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210400* -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
ACTINIDES
CANDU TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
COOLING SYSTEMS
DEUTERIUM
ELEMENTS
ENERGY SYSTEMS
ENERGY TRANSFER
EQUILIBRIUM
F CODES
FEEDBACK
FLUID FLOW
FLUID MECHANICS
H CODES
HEAT TRANSFER
HEAVY WATER MODERATED REACTORS
HYDRAULICS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
MATHEMATICAL MODELS
MECHANICS
METALS
NUCLEI
ODD-ODD NUCLEI
PRESSURE EFFECTS
PRESSURE TUBE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESEARCH PROGRAMS
S CODES
SIMULATION
STABILITY
STABLE ISOTOPES
THERMAL EQUILIBRIUM
THERMAL REACTORS
URANIUM
VOID FRACTION
210400* -- Power Reactors
Nonbreeding
Otherwise Moderated or Unmoderated
ACTINIDES
CANDU TYPE REACTORS
COMPUTER CODES
COMPUTERIZED SIMULATION
COOLING SYSTEMS
DEUTERIUM
ELEMENTS
ENERGY SYSTEMS
ENERGY TRANSFER
EQUILIBRIUM
F CODES
FEEDBACK
FLUID FLOW
FLUID MECHANICS
H CODES
HEAT TRANSFER
HEAVY WATER MODERATED REACTORS
HYDRAULICS
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
MATHEMATICAL MODELS
MECHANICS
METALS
NUCLEI
ODD-ODD NUCLEI
PRESSURE EFFECTS
PRESSURE TUBE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESEARCH PROGRAMS
S CODES
SIMULATION
STABILITY
STABLE ISOTOPES
THERMAL EQUILIBRIUM
THERMAL REACTORS
URANIUM
VOID FRACTION