Investigation of axial-void-propagation velocity profiles in BWR fuel bundles. Interim report
Technical Report
·
OSTI ID:5342126
This report describes the method of measuring axial void propagation velocity in the core of an operating BWR. Experimental data obtained from the noise signals of LPRM (Local Power Range Monitor) and TIP (Traversing In-Core Probe) detectors are compared to calculated steam velocity and kinematic wave velocity profiles. 25 figures.
- Research Organization:
- Washington Univ., Seattle (USA). Dept. of Nuclear Engineering
- OSTI ID:
- 5342126
- Report Number(s):
- EPRI-NP-2401; ON: DE82905365
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BWR TYPE REACTORS
DATA
ENRICHED URANIUM REACTORS
EXPERIMENTAL DATA
FLUID FLOW
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
IN CORE INSTRUMENTS
INFORMATION
MUEHLEBERG REACTOR
NUMERICAL DATA
POWER REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR INSTRUMENTATION
REACTOR NOISE
REACTORS
STEAM
THERMAL REACTORS
TWO-PHASE FLOW
VELOCITY
VOIDS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BWR TYPE REACTORS
DATA
ENRICHED URANIUM REACTORS
EXPERIMENTAL DATA
FLUID FLOW
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
IN CORE INSTRUMENTS
INFORMATION
MUEHLEBERG REACTOR
NUMERICAL DATA
POWER REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR INSTRUMENTATION
REACTOR NOISE
REACTORS
STEAM
THERMAL REACTORS
TWO-PHASE FLOW
VELOCITY
VOIDS
WATER COOLED REACTORS
WATER MODERATED REACTORS