Calculation of the scale factor for inference of pressurized water reactor core barrel motion from neutron noise spectral density
Journal Article
·
· Nucl. Technol.; (United States)
OSTI ID:6610471
To quantify the core barrel motion in a typical pressurized water reactor, a scale factor was calculated for both one- and two-dimensional geometries, using forward, variational, and perturbation methods of discrete-ordinates transport. The calculational results show that, although perturbation theory is adequate for estimating the scale factor, two-dimensional geometric effects are important enough to rule out the use of a one-dimensional approximation for all but the crudest calculations. Also, contributions of gamma rays can be ignored, and the results are relatively insensitive to the nuclear cross-section set employed. A method was then developed for inferring, with the aid of this scale factor, the magnitude of the core barrel motion from the following statistical descriptors: cross-power spectral density, auto-power spectral density, and amplitude probability density.
- Research Organization:
- Oak Ridge National Lab., TN
- OSTI ID:
- 6610471
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 40:1; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
Similar Records
Inference of core barrel motion from neutron noise spectral density. [PWR]
Quantification of core barrel motion using an analytically derived scale factor and statistical reactor noise descriptors. [PWR]
Core barrel motion calibration factor calculation. [PWR]
Technical Report
·
Mon Mar 14 23:00:00 EST 1977
·
OSTI ID:7312383
Quantification of core barrel motion using an analytically derived scale factor and statistical reactor noise descriptors. [PWR]
Journal Article
·
Tue Aug 01 00:00:00 EDT 1978
· Nucl. Technol.; (United States)
·
OSTI ID:6610467
Core barrel motion calibration factor calculation. [PWR]
Conference
·
Wed Dec 31 23:00:00 EST 1975
·
OSTI ID:7274538
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
ANALYTICAL SOLUTION
CORRELATIONS
FLUCTUATIONS
MECHANICAL VIBRATIONS
MONITORING
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
ANALYTICAL SOLUTION
CORRELATIONS
FLUCTUATIONS
MECHANICAL VIBRATIONS
MONITORING
MOTION
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR CORES
REACTOR INTERNALS
REACTOR NOISE
REACTORS
VARIATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS