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An Innovative Non-Destructive and Computational Method for Uranium Activity and Enrichment Verification of UF6 Cylinder

[+] Author Affiliations
Sayed A. El-Mongy, K. M. Allam

Atomic Energy Authority, Cairo, Egypt

Osama M. Farid

Reactors Department, ETRR 2, Inshas, Egypt

Paper No. ICONE14-89792, pp. 953-959; 7 pages
doi:10.1115/ICONE14-89792
From:
  • 14th International Conference on Nuclear Engineering
  • Volume 1: Plant Operations, Maintenance and Life Cycle; Component Reliability and Materials Issues; Codes, Standards, Licensing and Regulatory Issues; Fuel Cycle and High Level Waste Management
  • Miami, Florida, USA, July 17–20, 2006
  • Conference Sponsors: Nuclear Engineering Division
  • ISBN: 0-7918-4242-8 | eISBN: 0-7918-3783-1
  • Copyright © 2006 by ASME

abstract

Verification of 235 U enrichment in uranium hexaflouride (UF6 ) cylinders is often achieved by destructive and non-destructive assay techniques. These techniques are time consuming, need suitable and similar standard, in addition to loss of the nuclear material in the case of destructive analysis. This paper introduce an innovative approach for verifying of 235 U enrichment in UF6 cylinder. The approach is based on measuring dose rate (μSv/h) resulted from the emmitted gamma rays of 235 U at the surface of the cylinder and then calculating the activity of uranium and enrichment percentage inside the cylinder by a three dimensional model. Attenuation of the main 235 U gamma transitions due to the cylinder wall (5A Type of Ni alloy) was also caculated and corrected for. The method was applied on UF6 cylinders enriched with 19.75% of 235 U. 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 UF6 cylinder was found close to the target (certified) value (5.6 GBq) with 9% uncertainty. The method is being developed by taking into consideration other parameters.

Copyright © 2006 by ASME

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