Otman Jai

Spallation Yield of Neutrons Produced in Tungsten and Bismuth Target Bombarded with 0.1 to 3 GeV Proton Beam

M. Bencheikh, A. Didi, A. Dadouch, 2018, Moscow University Physics Bulletin.

Modelisation and distribution of neutron flux in radium–beryllium source (226Ra–Be)

A. Didi, A. Dadouch, Otman Jai, 2017 .

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

Otman Jai, T. E. Bardouni, O. Hajjaji, 2019 .

Neutron flux distribution in (Pb, Ta and W) target using accelerator of 18 MeV electron beam

M. Bencheikh, A. Didi, Otman Jai, 2018, Eurasian journal of physics and functional materials.

Monte Carlo transport code using for simulating the neutron yield of spallation targets: Uranium, Thorium, and Tantalum are used for an accelerator based on high proton beam

M. Bencheikh, A. Didi, A. Dadouch, 2018, 2018 4th International Conference on Optimization and Applications (ICOA).

Monte Carlo transport code use for optimisation of neutron flux produced with 10-18 MeV electron beam energy

M. Bencheikh, A. Didi, A. Dadouch, 2018 .

Monte Carlo simulation of thermal neutron flux of americium–beryllium source used in neutron activation analysis

M. Bencheikh, A. Didi, A. Dadouch, 2017 .

Spallation Yield of Neutrons Produced in Tungsten and Bismuth Target Bombarded with 0.1 to 3 GeV Proton Beam

M. Bencheikh, A. Didi, A. Dadouch, 2018, Moscow University Physics Bulletin.

Neutron activation analysis: Modelling studies to improve the neutron flux of Americium–Beryllium source

A. Didi, A. Dadouch, J. Tajmouati, 2017 .

Temperature distribution in the PGAA system: Collimator, shutter, and filter in TRIGA Mark II reactor

Otman Jai, Jamila Yousfi, A. Didi, 2024, Nuclear Analysis.