Radiation Dose Calculation Analysis During  The Dismantling of Disused Sealed Radioactive Sources at CNESTEN: MCNP Code Simulation Results

B. El Azzaoui; O. Kabach; R. Outayad; M. Y. Messous; K. Bergaoui; K. Nbaoui; J. Kadiri; E. Chakir; E. Alibrahmi; A. Kharchaf

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About The Authors

B. El Azzaoui
1. Materials Physics and Subatomics Laboratory, Physics Department, University Ibn Tofail, Kenitra, Morocco 2. National Center for Energy, Sciences and Nuclear Techniques (CNESTEN), Rabat, Morocco
Morocco

O. Kabach
Materials Physics and Subatomics Laboratory, Physics Department, University Ibn Tofail, Kenitra, Morocco
Morocco

R. Outayad
National Center for Energy, Sciences and Nuclear Techniques (CNESTEN), Rabat, Morocco
Morocco

M. Y. Messous
National Center for Energy, Sciences and Nuclear Techniques (CNESTEN), Rabat, Morocco
Morocco

K. Bergaoui
National Center of Nuclear Sciences and Technologies, Technopole Sidi Thabet, Tunisia
Tunisia

K. Nbaoui
Materials Physics and Subatomics Laboratory, Physics Department, University Ibn Tofail, Kenitra, Morocco
Morocco

J. Kadiri
Materials Physics and Subatomics Laboratory, Physics Department, University Ibn Tofail, Kenitra, Morocco
Morocco

E. Chakir
Materials Physics and Subatomics Laboratory, Physics Department, University Ibn Tofail, Kenitra, Morocco
Morocco

E. Alibrahmi
Materials Physics and Subatomics Laboratory, Physics Department, University Ibn Tofail, Kenitra, Morocco
Morocco

A. Kharchaf
Materials Physics and Subatomics Laboratory, Physics Department, University Ibn Tofail, Kenitra, Morocco
Morocco

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