INFERENCE OF CORE BARREL MOTION FROM NEUTRON NOISE SPECTRAL DENSITY

摘要

A method was developed for inference of core barrel motion from the following statistical descriptors:cross-power spectral density, auto-power spectral density, and amplitude probability density. To quantify the core barrel motion in a typical pressurized water reactor (PWR), a scale factor was calculated in both one- and two-dimensional geometries using forward, variational, and perturbation methods of discrete ordinates neutron transport. A procedure for selection of the proper frequency band limits for the statistical descriptors was developed.