skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

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

Abstract

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.

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

Citation Formats

Sweeney, F J, and Upadhyaya, B R. Measurement of core coolant flow velocities in PWRs using temperature: neutron noise cross correlation. United States: N. p., 1982. Web.
Sweeney, F J, & Upadhyaya, B R. Measurement of core coolant flow velocities in PWRs using temperature: neutron noise cross correlation. United States.
Sweeney, F J, and Upadhyaya, B R. Fri . "Measurement of core coolant flow velocities in PWRs using temperature: neutron noise cross correlation". United States. https://www.osti.gov/servlets/purl/6887538.
@article{osti_6887538,
title = {Measurement of core coolant flow velocities in PWRs using temperature: neutron noise cross correlation},
author = {Sweeney, F J and Upadhyaya, B R},
abstractNote = {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.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1982},
month = {1}
}

Conference:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this conference proceeding.

Save / Share: