Comparative Study Between Geant4, MCNP6 and Experimental Results Against Gamma Radiation Comes from a Cobalt-60 Source

The simulation codes based on the monte Carlo method are sophisticated averages and have become essential for dosimetry and radiation protection calculations close to the installations that handle radioactive sources. However, before starting to exploit these codes, they must be validated. The aim o...

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Veröffentlicht in:Moscow University physics bulletin 2020-09, Vol.75 (5), p.507-511
Hauptverfasser: El-Ouardi, Y., Dadouch, A., Aknouch, A., Mouhib, M., Maghnouj, A., Didi, A.
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container_end_page 511
container_issue 5
container_start_page 507
container_title Moscow University physics bulletin
container_volume 75
creator El-Ouardi, Y.
Dadouch, A.
Aknouch, A.
Mouhib, M.
Maghnouj, A.
Didi, A.
description The simulation codes based on the monte Carlo method are sophisticated averages and have become essential for dosimetry and radiation protection calculations close to the installations that handle radioactive sources. However, before starting to exploit these codes, they must be validated. The aim of this work is to validate two from the Monte Carlo simulation codes most used currently in the world , GEANT4 and MCNP6, for future use in dosimetry and radiation protection requirements in the BOukhalef Ionization Station (SIBO)/ Tangier, Morocco which manipulates a radioactive source of cobalt-60. The validation method is based on a comparison between the simulated results and those obtained by a Fricke system. The codes are well validated, indeed the simulation and experimental results were in good agreement.
doi_str_mv 10.3103/S0027134920050033
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title Comparative Study Between Geant4, MCNP6 and Experimental Results Against Gamma Radiation Comes from a Cobalt-60 Source
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