Neutron activation analysis: Modelling studies to improve the neutron flux of Americium–Beryllium source von Didi, Abdessamad, Dadouch, Ahmed, Jaï, Otman, Tajmouati, Jaouad, El Bekkouri, Hassane

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Modeling of the 2 MW TRIGA Mark-II Research Reactor Using the Deterministic Codes System DRAGON5 and DONJON5 von Jaï, Otman, El Hajjaji, Otman, El Bardouni, Tarek

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Validation of DRAGON4/DONJON4 simulation methodology for a typical MNSR by calculating reactivity feedback coefficient and neutron flux von Al Zain, Jamal, El Hajjaji, O., El Bardouni, T., Boukhal, H., Jaï, Otman

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Temperature feedback reactivity analysis for LEU-Fuelled SLOWPOKE-2 research reactor using DRAGON5 and DONJON5 codes von Jaï, Otman, El Hajjaji, Otmane, Didi, Abdessamad

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Modelisation and distribution of neutron flux in radium–beryllium source (226Ra–Be) von Didi, Abdessamad, Dadouch, Ahmed, Jai, Otman

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Monte Carlo simulation of thermal neutron flux of americium–beryllium source used in neutron activation analysis von Didi, Abdessamad, Dadouch, Ahmed, Bencheikh, Mohamed, Jai, Otman

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Deterministic Analysis of the Low Enriched Uranium SLOWPOKE-2 Research Reactor Using DRAGON-5 and DONJON-5 Codes System von Jai, Otman, El Hajjaji, Otman, El Bardouni, Tarek, Didi, Abdessamad

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Spallation Yield of Neutrons Produced in Tungsten and Bismuth Target Bombarded with 0.1 to 3 GeV Proton Beam von Didi, Abdessamad, Bencheikh, Mohamed, Dadouch, Ahmed, El Bekkouri, Hassane, Tajmouati, Jaouad, Maghnouj, Abdelmajid, Jai, Otman

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Toward for production of Molybdenum-99 by irradiation of MoO3 target in a neutron flux von Didi, Abdessamad, Dadouch, Ahmed, Jai, Otman, Bouhali, Fatima Zahra

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Neutron activation analysis: Modelling studies to improve the neutron flux of Americiume-Beryllium source von Abdessamad Didi, Ahmed Dadouch, Otman Jaï, Jaouad Tajmouati, Hassane El Bekkouri

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Temperature distribution in the PGAA system: Collimator, shutter, and filter in TRIGA Mark II reactor von Yousfi, Jamila, Didi, Abdessamad, Lemziouka, Hamane, Mrharrab, Lamiae, Amsil, Hamid, Jai, Otman, Bounouira, Hamid, Larakil, Khalid

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Neutron flux distribution in (Pb, Ta and W) target using accelerator of 18 MeV electron beam von Didi, Abdessamad, Dadoucha, Ahmed, Jai, Otman, Bencheikh, Mohamed

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Neutron activation analysis: Modelling studies to improve the neutron flux of Americium-Beryllium source von Didi, Abdessamad, Dadouch, Ahmed, Jai, Otman, Tajmouati, Jaouad, Bekkouri, Hassane El

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