Published 1986 | Version v1
Report

Determination of the sensitivity volume of a BWR in-core detector

Description

Reactor noise analysis is used to draw dynamic information while a nuclear reactor is operating at a steady power. By cross correlating the signal fluctuations (i.e. cross power spectral density (CPSD)) of two axially located detectors in a boiling water reactor (BWR), one can evaluate a velocity associated with the propagating noise. In the past several years, attention of several investigators has been devoted to the interpretation of this velocity. Determination of the detector sensitivity volume (i.e. field-of-view (FOV)) is needed because it is important to know if the measured velocity is an average or a localized quantity. By performing a series of 2-group, X-Y, S4 transport theory calculations, it is concluded that a cell homogeneous model is valid for the prediction of the adjoint function distribution around a line (i.e. infinite in Z) detector. The validity of the cell homogeneous model for the prediction of the adjoint function around a point detector (i.e. a finite detector) is confirmed by performing numerical (2-group, cell and bundle homogeneous, X-Y and X-Y-Z diffusion theory models) and analytical (1-D infinite homogeneous diffusion theory model) calculations. Comparison of the results of the combined method of transport and diffusion theories with the results obtained from diffusion theory, showed that an X-Y-Z cell homogeneous diffusion theory model is sufficient for the prediction of the detector FOV

Availability note (English)

University Microfilms Order No. 87-06,577.

Additional details

Publishing Information

Imprint Pagination
208 p.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
19063838
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Thesis, Non-conventional Literature
Descriptors DEI
BWR TYPE REACTORS; COMPARATIVE EVALUATIONS; IN CORE INSTRUMENTS; NEUTRON DIFFUSION EQUATION; NEUTRON TRANSPORT THEORY; REACTOR NOISE; SENSITIVITY; VELOCITY; VOLUME
Descriptors DEC
ENRICHED URANIUM REACTORS; EVALUATION; POWER REACTORS; REACTORS; THERMAL REACTORS; TRANSPORT THEORY; WATER COOLED REACTORS; WATER MODERATED REACTORS