Absolute Measurements for Uranium Verification Content in Radiographic Containers

Authors

  • H. I. Khedr Egyptian Nuclear and Radiological Regulatory Authority (ENRRA)
  • Z. Ahmed Egyptian Nuclear and Radiological Regulatory Authority (ENRRA)
  • M. Gad Egyptian Nuclear and Radiological Regulatory Authority (ENRRA)

Keywords:

Radiographic Containers, Uranium Verification

Abstract

Depleted Uranium (DU) is used for its very high density in civilian uses include radiation shielding in medical radiation therapy, industrial radiography equipment, containers used to transport radioactive materials. Absolute measurements have been performed for verification of uranium mass content in gamma radiography by using detector’s model developed with MCNP in nuclear safeguard inspection for these samples. Both the experimental results obtained as well as MCNP results are used to estimate the 238U mass content. The determined and the declared 238U masses values are found in an agreement with accuracy from -1.74 % to 1.80 %.

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Published

2020-04-17

How to Cite

Khedr, H. I. ., Ahmed, Z. ., & Gad, M. . (2020). Absolute Measurements for Uranium Verification Content in Radiographic Containers. American Scientific Research Journal for Engineering, Technology, and Sciences, 67(1), 66–72. Retrieved from https://www.asrjetsjournal.org/index.php/American_Scientific_Journal/article/view/5775

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