Measurement of core coolant flow velocities in PWRs using temperature: neutron noise cross correlation

Conference · Fri Jan 01 00:00:00 EST 1982

OSTI ID:6887538

Sweeney, F J; Upadhyaya, B R

To study the relationship between the time delay inferred from this phase angle and core coolant flow velocities, noise measurements were performed at the Loss of Fluid Test Facility (LOFT) reactor and at a commercial PWR. In-core, self-powered neutron detector (SPND) noise at LOFT and ex-core ionization chamber noise at the commercial PWR were cross correlated with core exit temperature noise. Time delays were inferred from the slope of the phase angle versus frequency plots over the frequency range from 0.05 to 2.0 Hz.

• Research Organization: Oak Ridge National Lab., TN (USA); Tennessee Univ., Knoxville (USA); Analysis and Measurement Services, Knoxville, TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6887538
• Report Number(s): CONF-821103-40; ON: DE83003408
• Resource Relation: Conference: American Nuclear Society winter meeting, Washington, DC, USA, 14 Nov 1982
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LOFT REACTOR
PRIMARY COOLANT CIRCUITS
REACTOR NOISE
FLUID FLOW
HYDRAULICS
PWR TYPE REACTORS
COOLANTS
CORRELATIONS
FLOW RATE
IONIZATION CHAMBERS
REACTOR CORES
SELF-POWERED NEUTRON DETECTORS
VELOCITY
COOLING SYSTEMS
ENERGY SYSTEMS
FLUID MECHANICS
MEASURING INSTRUMENTS
MECHANICS
NEUTRON DETECTORS
RADIATION DETECTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
SELF-POWERED DETECTORS
TANK TYPE REACTORS
TEST REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled