Quantification of core barrel motion using an analytically derived scale factor and statistical reactor noise descriptors. [PWR]
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:6610467
A method was developed for quantitative inference of core barrel motion from the following statistical descriptors using an analytically derived scale factor (SF): cross-power spectral density (CPSD), auto-power spectral density, and amplitude probability density (APD). The proper frequency band over which to compute the statistical descriptors is conveniently determined from the coherence and phase information from two ex-core power range neutron monitors positioned diametrically across the reactor vessel. Core barrel motion can then be quantified from the integral of the band-limited CPSD of two diametrically opposed excore monitors or, if the coherence between the pair is > or approximately 0.7, from a properly band-limited APD function. Wide-band APD and CPSD functions were both demonstrated to yield erroneous estimates for the magnitude of core barrel motion.
- Research Organization:
- Oak Ridge National Lab., TN
- OSTI ID:
- 6610467
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 40:1; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
CORRELATIONS
FLUCTUATIONS
MECHANICAL VIBRATIONS
MOTION
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR INTERNALS
REACTOR NOISE
REACTORS
VARIATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
CORRELATIONS
FLUCTUATIONS
MECHANICAL VIBRATIONS
MOTION
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR INTERNALS
REACTOR NOISE
REACTORS
VARIATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS