Development of Robotic Analysis for Mixed Oxide Sample by X-ray Fluorescence and Gamma-ray Spectrometric Method

Year
1993
Author(s)
Seiji Uchikoshi - Nuclear Material Control Center
M. Ishikawa - Nuclear Material Control Center
M. Midorikawa - Nuclear Material Control Center
Abstract
An automated analytical system for mixed oxide samples has been developed to increase the analytical capability and to improve the timeliness of measurements at conversion and mixed oxide fuel fabrication plants. The analytical system is divided into a sample preparation system, an X-ray fluorescence spectrometer, a gamma-ray spectrometer, and a computer system for control and data processing. Concentrations of uranium and Plutonium are determined by measuring the intensity of the L series X-ray lines of each element. The isotope composition of plutonium in the sample powder is also determined without sample pretreatment by passive gamma-ray spectrometry. The system was modified to enhance reliability of the system operation and to improve accuracy of the analytical results. After modification, the results obtained with a test of this system on 0.2 g of U^OQ had a precision of 0.3 - QA% (RSD, n=9) and an accuracy of ±0.3% (relative deviation of mean value).