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Title: In-core coolant flow monitoring of pressurized water reactors using temperature and neutron noise

Abstract

Noise measurements were performed at the Loss-of-Fluid-Test (LOFT) and Sequoyah-1 pressurized water reactors (PWRs) in order to investigate the possibility of inferring in-core coolant velocities from cross-power spectral density (CPSD) phases of core-exit thermocouple and in-core neutron detector signals. These noise measurements were used to investigate the effects of inlet coolant temperature, core flow, reactor power, and random heat transfer fluctuations on the noise-inferred coolant velocities. The effect on the inferred velocities of varying in-core neutron detector and core-exit thermocouple locations was also investigated. Theoretical models of temperature noise were developed, and the results were used to interpret the experimental measurements. Results of these studies indicate that the neutron detector/thermocouple phase is useful for monitoring core flow in PWRs. Results show that the interpretation of the phase between these signals depends on the source of temperature noise, the response times and locations of the sensors, and the neutron dynamics of the reactor. At Sequoyah-1 we found that the in-core neutron detector/core-exit thermocouple phase can be used to infer in-core coolant velocities, provided that the measurements are corrected for the thermocouple response time.

Authors:
; ;
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (USA); Tennessee Univ., Knoxville (USA)
OSTI Identifier:
6280225
Report Number(s):
CONF-841017-8
ON: DE85002468
DOE Contract Number:  
AC05-84OR21400
Resource Type:
Conference
Resource Relation:
Conference: Specialists' meeting on reactor noise - SMORN IV, Dijon, France, 15 Oct 1984; Other Information: Portions are illegible in microfiche products
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PWR TYPE REACTORS; FLUID FLOW; LOFT REACTOR; REACTOR NOISE; SEQUOYAH-1 REACTOR; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 210200* - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Sweeney, F J, Upadhyaya, B R, and Shieh, D J. In-core coolant flow monitoring of pressurized water reactors using temperature and neutron noise. United States: N. p., 1984. Web.
Sweeney, F J, Upadhyaya, B R, & Shieh, D J. In-core coolant flow monitoring of pressurized water reactors using temperature and neutron noise. United States.
Sweeney, F J, Upadhyaya, B R, and Shieh, D J. 1984. "In-core coolant flow monitoring of pressurized water reactors using temperature and neutron noise". United States. https://www.osti.gov/servlets/purl/6280225.
@article{osti_6280225,
title = {In-core coolant flow monitoring of pressurized water reactors using temperature and neutron noise},
author = {Sweeney, F J and Upadhyaya, B R and Shieh, D J},
abstractNote = {Noise measurements were performed at the Loss-of-Fluid-Test (LOFT) and Sequoyah-1 pressurized water reactors (PWRs) in order to investigate the possibility of inferring in-core coolant velocities from cross-power spectral density (CPSD) phases of core-exit thermocouple and in-core neutron detector signals. These noise measurements were used to investigate the effects of inlet coolant temperature, core flow, reactor power, and random heat transfer fluctuations on the noise-inferred coolant velocities. The effect on the inferred velocities of varying in-core neutron detector and core-exit thermocouple locations was also investigated. Theoretical models of temperature noise were developed, and the results were used to interpret the experimental measurements. Results of these studies indicate that the neutron detector/thermocouple phase is useful for monitoring core flow in PWRs. Results show that the interpretation of the phase between these signals depends on the source of temperature noise, the response times and locations of the sensors, and the neutron dynamics of the reactor. At Sequoyah-1 we found that the in-core neutron detector/core-exit thermocouple phase can be used to infer in-core coolant velocities, provided that the measurements are corrected for the thermocouple response time.},
doi = {},
url = {https://www.osti.gov/biblio/6280225}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1984},
month = {1}
}

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