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Monte Carlo validation of dose mapping for the Tunisian Gamma Irradiation Facility using the MCNP6 code

  • Published:2020-08 Issue: Volume:173 Page:108942
  • ISSN:0969-806X
  • Container-title:Radiation Physics and Chemistry
  • language:en
  • Short-container-title:Radiation Physics and Chemistry

Author:

Dridi W.,Daoudi M.,Farah K.,Hosni F.

Publisher

Elsevier BV

Subject

Radiation

Reference28 articles.

1. Introduction to Radiological Physics and Radiation Dosimetry;Attix,2004

2. MCNP:A General Monte Carlo N-Particle Transport Code, Version 4C;Briesmeister,2000

3. Principles of Radiation Shielding;Chilton,1984

4. Dosimetry commissioning for an industrial Cobalt-60 gamma-radiation facility;Covaco;Appl. Radiat. Isot.,1991

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