MEASURING APPARATUS FOR AVERAGE BURNUP OF NUCLEAR FUEL ASSEMBLY

摘要

PURPOSE:To enable measurement of an average burnup in a short time by providing detectors in the number of (n) (6=n=3) for obtaining data on combustion, a burnup calculating means, a measured data check program element, an average burnup calculating means, etc. CONSTITUTION:In accordance with a method of calculation of an average burnup of a nuclear fuel assembly 1, measured data on an axial-direction relative burnup distribution and one or several burnup data for determining the average burnup of the assembly from detectors in the number of (n) (6=n=3), on one hand, and measured data on the burnup from the detectors in the number of (n) (6=n=3), on the other, are sent to a processing element from each detector in a detecting element 2. In an interpolation processing program element 3 subsequent to the detecting element 2, an arithmetic processing for obtaining a relative value or the burnup at a position in the axial direction which is not measured is executed by functional approximation by several-degree polynominal approximation or several-degree Fourrier series approximation. After the interpolation processing is completed, an average burnup of the measured assembly 1 is determined in an assembly average burnup calculation program element 4 and it is subjected to an output processing in CRT 7 and an output element 8 such as a printer.