Search Results - El Hajjaji, Otman

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  1. 1
    Neutron conversion coefficients of ambient dose equivalent and personal dose equivalent

    Neutron conversion coefficients of ambient dose equivalent and personal dose equivalent by Kanti, Hassan Al, Hajjaji, Otman El, Bardouni, Tarek El, Mohammed, Maged

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  2. 2
    Modeling of the 2 MW TRIGA Mark-II Research Reactor Using the Deterministic Codes System DRAGON5 and DONJON5

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

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  3. 3
    Deterministic Analysis of the Low Enriched Uranium SLOWPOKE-2 Research Reactor Using DRAGON-5 and DONJON-5 Codes System

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

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  4. 4
    Empowering nuclear reactor analysis: OpenNode for accurate 3D core simulation through nodal expansion neutron diffusion equations solving

    Empowering nuclear reactor analysis: OpenNode for accurate 3D core simulation through nodal expansion neutron diffusion equations solving by Satti, Hicham, El Hajjaji, O.

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  5. 5
    Advancing Fixed-Source Reactor Analysis Through OpenNode Implementation

    Advancing Fixed-Source Reactor Analysis Through OpenNode Implementation by Satti, Hicham, El Hajjaji, Otman, El Bardouni, Tarek, Mira, Mohamed, Nouayti, Abdelhamid

    Published in Nuclear technology
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  6. 6
    Verification of Adjoint Solution Commutativity with the New OpenNode Nodal Diffusion Code

    Verification of Adjoint Solution Commutativity with the New OpenNode Nodal Diffusion Code by Satti, Hicham, El Hajjaji, Otman, Bardouni, Tarek El, Ghalbzouri, Tarik El

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  7. 7
    Simulation of a NaI(Tl) detector model using OpenMC modified on code source and validation using experimental and simulated results

    Simulation of a NaI(Tl) detector model using OpenMC modified on code source and validation using experimental and simulated results by Drissi El-Bouzaidi, Mohamed, El Bardouni, T., El Hajjaji, Otman, Idrissi, Abdelghani, Chham, Essaid, Pérez, Abel Milena, Mira, Mohamed

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  8. 8
    Re-evaluation of 18 F-FDG absorbed and effective dose in adult and pediatric phantoms using DoseCalcs Monte Carlo platform: a validation study

    Re-evaluation of 18 F-FDG absorbed and effective dose in adult and pediatric phantoms using DoseCalcs Monte Carlo platform: a validation study by El Ghalbzouri, Tarik, El Bardouni, Tarek, El Bakkali, Jaafar, El Hajjaji, Otman, Satti, Hicham, Arectout, Assia, Hadouachi, Maryam, Yerru, Randa

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  9. 9
    Re-evaluation of $$^{18}$$F-FDG absorbed and effective dose in adult and pediatric phantoms using DoseCalcs Monte Carlo platform: a validation study

    Re-evaluation of $$^{18}$$F-FDG absorbed and effective dose in adult and pediatric phantoms using DoseCalcs Monte Carlo platform: a validation study by El Ghalbzouri, Tarik, El Bardouni, Tarek, El Bakkali, Jaafar, El Hajjaji, Otman, Satti, Hicham, Arectout, Assia, Hadouachi, Maryam, Yerru, Randa

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  10. 10
    Temperature feedback reactivity analysis for LEU-Fuelled SLOWPOKE-2 research reactor using DRAGON5 and DONJON5 codes

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

    Published in Nuclear Analysis
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  11. 11
    Validation of DRAGON4/DONJON4 simulation methodology for a typical MNSR by calculating reactivity feedback coefficient and neutron flux

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

    Published in Results in physics
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