Published 1991 | Version v1
Report

Development of automated analytical system for mixed oxide sample by X-ray and gamma-ray spectrometric method

  • 1. Nuclear Material Control Center, Tokyo (Japan)

Description

An automated analytical system for mixed oxide sample has been developed to increase analytical capability as well as to improve timeliness of measurement at the conversion and the mixed oxide fuel fabrication plants. The analytical system ca be divided into a sample preparation system, an x-ray fluorescence and a gamma-ray spectrometer, and a computer system for operation control and data processing. The sample preparation system consists of two revolute robots and various kinds of component devices such as a sample and a crucible storage, a sampling device with a balance, an electric furnace and so on. In this system 0.3 g of sample and 7 g of anhydrous sodium tetraborate are taken and fused in a platinum crucible at 1100 deg C for ten minutes to prepare a glass bead disk. Concentrations of uranium and plutonium are determined by measuring intensity of L series x-ray line of each element. Isotope composition of plutonium in the sample is also determined by passive gamma-ray spectrometry without sample pre-treatment

Part of:
Safeguards and Nuclear Material Management

Additional details

Publishing Information

Imprint Title
Safeguards and nuclear material management
Imprint Pagination
745 p.
Journal Page Range
p. 245-249.
Report number
EUR--13686

Conference

Title
13. Annual Symposium on Safeguards and Nuclear Material Management.
Dates
14-16 May 1991.
Place
Avignon (France).

Optional Information