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pro vyhledávání: '"Khalid Oulabbes"'
Autor:
Sanae El Ouahdani, Hassane El Bekkouri, Ahmed Dadouch, Otman Jai, Mohamed Bencheikh, Abdessamad Didi, Khalid Oulabbes
Publikováno v:
International Journal of Nuclear Energy Science and Technology. 12:324
The MCNP code based on the Monte Carlo model is intended for neutron simulations. It is used to study neutron production, neutron flux calculations, energy deposition, dose, and multiplicity of neutrons; in this paper, we used the MCNP6 code for neut
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::1c8bb65091d52ec8ec829936b3db9e2b
https://doi.org/10.1504/ijnest.2018.097155
https://doi.org/10.1504/ijnest.2018.097155
