Review of Equipment Used in Russian Practice for Accounting Measurements of Nuclear Materials

Year
1999
Author(s)
Lev Neymotin - Brookhaven National Laboratory
V. V. Sviridova - VNIIA
Abstract
The objective of this work was to analyze instrumentation and methodologies used at Russian nuclear facilities for measurement of item nuclear materials, materials in bulk for, and waste streams; specify possibilities for the application of accounting measurements; and develop recommendations for improvement. The major steps and results: Representative conversion, enrichment (gas centrifuge), fuel fabrication, spent fuel reprocessing and chemical-metallurgical production facilities in Russia were selected; Full lists of nuclear materials were prepared; information about measurements methods and instrumentation for each type of nuclear material were gathered; and Recommendations on methodological an instrumentation support of accounting measurements for all types of materials were formulated The analysis showed that the existing measurement methods and instrumentation serve mostly to support the technological process control and nuclear an radiation safety control. Requirements for these applications are lowr than requirements for MC&A applications. to improve the state of MC&A at Russian nuclear facilities, significant changes in instrumentation support will be required, specifically in weighing equipment, volume measurements, and destructive and non-destructive analysis equipment, along with certified reference materials. The three major issues to be addressed are: development and certification of new measurement methods, certification of measurement equipment training of MC&A personnel