Development and Validation of an MCNP model for a Broad-Energy Germanium Detector

Authors

  • M. Abdelati Safeguards & Physical Protection Department, Egyptian Nuclear and Radiological Regulatory Authority, P.O.Box 7551, Nasr City, 11762 Cairo, Egypt
  • H. I. Khedr Safeguards & Physical Protection Department, Egyptian Nuclear and Radiological Regulatory Authority, P.O.Box 7551, Nasr City, 11762 Cairo, Egypt
  • K. M. El Korughly Safeguards & Physical Protection Department, Egyptian Nuclear and Radiological Regulatory Authority, P.O.Box 7551, Nasr City, 11762 Cairo, Egypt

Keywords:

MCNP model, Falcon 5000 detector, MCNP efficiencies, activity, 235U mass contents, standard NM sample.

Abstract

An MCNP model was developed for a Broad-Energy Germanium Detector (Model BE2830). This model was constructed based on the manufacturer specifications provided for the detector. In order to develop the complete MCNP model, the activity of three standard radioactive sources (Co-57, Co-60 and Cs-137) was calculated by estimating the detector absolute full energy peak efficiency at different gamma-ray energy lines, using the MCNP model, and measuring count rates due to those energy lines, using the BEGe detector, with different setup configurations. The obtained results were in agreement with certified values with a relative difference ranging from -1.84% to 1.57%. As an application for the constructed MCNP model, 235U mass contents for five Standard Nuclear material (SNM) samples were estimated. The obtained results indicate that this model could be used effectively for nuclear safeguards purposes.

References

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Published

2018-01-20

How to Cite

Abdelati, M., Khedr, H. I., & El Korughly, K. M. (2018). Development and Validation of an MCNP model for a Broad-Energy Germanium Detector. American Scientific Research Journal for Engineering, Technology, and Sciences, 39(1), 73–81. Retrieved from https://asrjetsjournal.org/index.php/American_Scientific_Journal/article/view/3640

Issue

Vol. 39 No. 1 (2018)

Section

Articles

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