Abstract
Verification of 235U enrichment in uranium hexafluoride (UF 6) cylinders is often achieved by destructive (DA) and non-destructive assay (NDA) techniques. These techniques are time consuming and need suitable and similar standard. This is in addition to the loss of nuclear material in the case of destructive analysis. This paper introduces an innovative approach for verifying of 235U enrichment in UF 6 cylinder. The approach is based on measuring dose rate ( μ Sv / h ) due to the emitted gamma rays of 235U at the surface of the cylinder and then calculating the activity of uranium and enrichment percentage inside the cylinder by a developed three dimensional model. Attenuation of the main 235U gamma transitions due to the cylinder wall (5B type of Ni alloy) was also calculated and corrected for. The method was applied on UF 6 cylinders enriched with 19.75% of 235U. The calculated enrichment was found to be 18% with 9% uncertainty. By the suggested method, the calculated total uranium activity inside one of the investigated UF 6 cylinder was found close to the target (certified) value (5.6 GBq) with 9% uncertainty. The method is currently developed by taking into consideration other parameters.
Sign-in/Register to access full text options 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
