AN OVERVIEW OF MEASUREMENT METHODS FOR SPECIAL NUCLEAR MATERIAL IN SPENT NUCLEAR FUEL

Year
1989
Author(s)
Bruce W. Moran - Martin Marietta Energy Systems, Inc.
Abstract
Summary results from a survey of nondestructive assay measurement methods applicable to the measurement of the special nuclear material content of spent nuclear fuel are described. The role of nuclear material measurements in the domestic and international safeguarding of spent nuclear fuel in the United States' federal waste management system has yet to be determined. An understanding of the characteristics and capabilities of the potentially applicable measurement systems should provide valuable information to the developers of the safeguards approaches for the monitored retrievable storage and final disposal systems. The discussion focuses on the general characteristics of the identified direct and indirect measurement methods.