Identification of two-phase flow regimes by neutron noise analysis
- Institute of Nuclear Energy Research, Lung-Tan (Taiwan)
- National Tsing Hua Univ., Hsinchu (Taiwan). Dept. of Nuclear Engineering
A new technique is proposed for analyzing neutron noise signals to identify two-phase flow patterns in an experimental reactor. Based on the modeling of neutron signals by autoregressive moving average models via an optimization technique, two-phase flow patterns can be identified by a single index known as the dynamic signature. A computer code is set up in an IBM-PC/XT microcomputer by which --90% of the experimental cases have been successfully identified among 86 data sets. This technique is recommended for the analysis of boiling water reactor neutron signals to generate a data base for designing a core flow monitoring system. This technique would be useful in understanding thermohydraulic phenomena in an operating power reactor.
- OSTI ID:
- 5412097
- Journal Information:
- Nuclear Technology; (USA), Journal Name: Nuclear Technology; (USA) Vol. 86:1; ISSN NUTYB; ISSN 0029-5450
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400 -- Nuclear Reactor Technology-- Control Systems
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
42 ENGINEERING
420400 -- Engineering-- Heat Transfer & Fluid Flow
BARYONS
BWR TYPE REACTORS
COMPUTER CODES
COMPUTERS
DATA BASE MANAGEMENT
DESIGN
DIGITAL COMPUTERS
ELEMENTARY PARTICLES
EXPERIMENTAL REACTORS
FERMIONS
FLUID FLOW
FLUID MECHANICS
HADRONS
HYDRAULICS
IBM COMPUTERS
MANAGEMENT
MECHANICS
MICROCOMPUTERS
MONITORING
NEUTRONS
NOISE
NUCLEONS
OPTIMIZATION
PERSONAL COMPUTERS
REACTOR COMPONENTS
REACTOR CORES
REACTOR MONITORING SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
THERMODYNAMICS
TWO-PHASE FLOW
WATER COOLED REACTORS
WATER MODERATED REACTORS