Physical treatise on the determination of burn-up, neutron fluence, as well as fission product and heavy metal concentrations on individual fuel elements

Automatic translation: Any reprocessing of nuclear fuel required the preparation of a reliable material balance for a large number of nuclides, some of which obtained in as chemically pure a form as possible (product specification), another separated from long-lived radioactive nuclides (waste treatment) and one further in the successive individual processes should be controlled (gap flow control). From these nuclides, either directly through fission or capture or indirectly through subsequent decay, fissile heavy metal nuclides are of particular interest (Nuclear Non-Proliferation Treaty). The material balance therefore requires a representative starting value for the residual fissile material content undestroyed nuclear fuel for reprocessing. At the same time it is pointed out that only indirect determination methods are used here are applicable.