Power density distribution control exemplified by the Bilibin NPP reactors

The solution of the problem on neutron density determination (energy release power capacities) in reactor fuel channels on thermal neutrons on flux measuring in discrete points - openings in graphite brickwork by self-powered detectors or according to regulating ''rods weighing'' results. The determination is carried out by the method of plane interpolation of fluxes between the reference points, taking into account flux distortions nearby the regulating rods, void cells and other inhomogeneities. The distortion character and statistic properties of interpolated magnitudes for method accuracy calculation are obtained from physical starting measurements of flux distributions by fission chambers. The method introduced at the Bilibin NPP reactors is characterized by the error approximately 5% at the flux reduction in 273 fuel channels over 24 reference points and presence in the zone of a great number (approximately 60) inhomogeneities as regulating rods and void cells