Nuclear Engineering and Technology

  • 제49권4호
  • /
  • Pages.787-791
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  • 2017
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Neutron activation analysis: Modelling studies to improve the neutron flux of Americium-Beryllium source

  • Didi, Abdessamad (Advanced Technology and Integration System, Department of Physics, Faculty of Science Dhar Mehraz, University Sidi Mohamed Ben Abdellah) ;
  • Dadouch, Ahmed (Advanced Technology and Integration System, Department of Physics, Faculty of Science Dhar Mehraz, University Sidi Mohamed Ben Abdellah) ;
  • Jai, Otman (Laboratory of Radiation and Nuclear Systems, Department of Physics, Faculty of Sciences) ;
  • Tajmouati, Jaouad (Advanced Technology and Integration System, Department of Physics, Faculty of Science Dhar Mehraz, University Sidi Mohamed Ben Abdellah) ;
  • Bekkouri, Hassane El (Advanced Technology and Integration System, Department of Physics, Faculty of Science Dhar Mehraz, University Sidi Mohamed Ben Abdellah)
  • 투고 : 2016.09.15
  • 심사 : 2017.02.02
  • 발행 : 2017.08.25
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초록

Americium-beryllium (Am-Be; n, ${\gamma}$) is a neutron emitting source used in various research fields such as chemistry, physics, geology, archaeology, medicine, and environmental monitoring, as well as in the forensic sciences. It is a mobile source of neutron activity (20 Ci), yielding a small thermal neutron flux that is water moderated. The aim of this study is to develop a model to increase the neutron thermal flux of a source such as Am-Be. This study achieved multiple advantageous results: primarily, it will help us perform neutron activation analysis. Next, it will give us the opportunity to produce radio-elements with short half-lives. Am-Be single and multisource (5 sources) experiments were performed within an irradiation facility with a paraffin moderator. The resulting models mainly increase the thermal neutron flux compared to the traditional method with water moderator.

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