Year
1970
Abstract
The independent features of the power fuel cycle in which material is fabricated, irradiated, and recovered at different facilities provide a basis for potential independent cross-checks. One general class of cross-checks for plutonium arises from the inherent relationships between the growth and depletion of the various nuclides undergoing irradiation. These relationships are such that at the end of core life, the concen- trations of the various nuclides accompanying the plutonium give testimony to the plutonium content. One such relationship which relates the 235U depletion of U observed between fabrication and end of irradiation to plutonium content is discussed in some detail. Measurements of spent fuel from the Yankee Rowe Reactor are used to illustrate potential safeguards value. As a corollary to this work, the potential safeauards values of spent fuel measurements relating to burnup are also briefly described and referenced.