235U enrichment or UF6 mass determination on UF6 cylinders with non-destructive analysis methods

Abstract The measurement of the 235 U enrichment and the mass of UF 6 in 30B and 48Y transit cylinders are important safeguards verification tasks of IAEA. In the framework of a project aiming to establish an unattended measurement station at isotope enrichment facilities (Lebrun, 2007) [1] , a study was carried out to describe the state-of-the-art of non-destructive assay methods applicable to UF 6 cylinders. The objective of the present work is to provide a feasibility assessment study of all known NDA techniques applicable to the quantitative verification of all uranium categories involved in an enrichment processing plant. Based on this investigation, the most appropriate techniques were then investigated for suitability of use in an unattended measurement station.