原子炉内出力分布の測定方法及びその装置

深谷 裕司; 中川 繁昭; 沖田 将一朗

not registered

A method of measuring a power distribution in a reactor core is based on a neutron transport equation representing the relationship between power densities of a plurality of fuel elements within a pressure vessel of the nuclear reactor, output signals from neutron detectors at a plurality of locations, and detector sensitivity with respect to the positions of the fuel elements and the neutron detectors. A detector sensitivity matrix represents the sensitivities of each neutron detector location to the power density at each fuel element position. The power distribution is calculated from the product of the matrix the output signals of the neutron detectors and the pseudo-inverse of the detector sensitivity matrix. The neutron detectors may be positioned inside or outside the reactor pressure vessel. The measured power distribution may be considered valid when the rank of the pseudo-inverse matrix is greater than or equal to 0.8n, where n is the number of fuel elements.