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Jamal Al-Zain

Jamal Al-Zain

LiveDNA ID: 969.36624
14 Publications
0 Editorial Roles
0 Projects

About

Professional Summary

Assistant Professor and nuclear physicist with more than a decade of research experience in reactor physics, neutron transport, and in medical-physics applications (photon-beam radiotherapy dosimetry). Ph.D. in Nuclear Science and Technology with specialised expertise in the development and validation of coupled neutronics–thermal-hydraulics models for research reactors (notably MNSR, PWR and TRIGA Mark II), fuel depletion and activity-inventory analyses, and Monte Carlo / deterministic transport methods. Proficient user of DRAGON5/DONJON5, MCNP6, MAKXSF, OpenMC, ONIX, PARET/ANL, and Geant4/GAMOS, and the NJOY/FRENDY nuclear-data processing chain, with demonstrated ability to benchmark evaluated nuclear data libraries (ENDF/B-VII.1, ENDF/B-VIII.0, JEFF-3.3, JENDL-5). Author of 25+ peer-reviewed publications in leading nuclear engineering journals; active peer reviewer for ten international journals and Guest Editor for Nuclear Engineering and Design. Recipient of the Best Researcher Award (International Young Scientist Awards, 2025).

Education

Academic Background
  • Ph.D. Abdelmalek Essaadi University, Morocco Applied Nuclear Physics | Completed: 2022
  • Ph.D. Student Abdelmalek Essaâdi University, Morocco Nuclear Science and Engineering | Completed: 2018
  • M.Sc. Abdelmalek Essaâdi University, Morocco Nuclear Radiation and Nuclear Physics | Completed: 2017
  • B.Sc. Sana'a University, Yemen Applied Physics | Completed: 2003

Publications (14)

Selected Scholarly Contributions
Development and implementation of a numerical simulation system for analyzing the thermal-hydraulic (T-H) characteristics of the MNSR research reactor fuel assembly
Jamal Al-Zain, O. El Hajjaji, T. El Bardouni, Ahmed A. Basfar, Ibrahim A. Alnaser, M. Lahdour, A. Abdelghafar Galahom, Y. Boulaich, Abdulaziz Ahmed, Mohamed Mira
Nuclear Engineering and Design | Journal Article
10.1016/j.nucengdes.2023.112759
Crossref
2024
Benchmark comparisons of OpenMC and DRAGON5 codes for calculating the doppler coefficient of reactivity.
Al-Zain, J., O. El Hajjaji, T. El Bardouni, M. Lahdour, M. Mira, H. Satti and H. El Yaakoubi,
Moscow Univ. Phys. Bull., | Journal Article
10.3103/S0027134922060169
Self Jamal Al-Zain
2022
NTP-ERSN verification with C5G7 1D extension benchmark and GUI development.
Lahdour, M., T.E. Bardouni, O.E. Hajjaji, E. Chakir, M. Mohammed, J.A. Zain and H. Ziani,
Nucl. Eng. Technol., | Journal Article
10.1016/j.net.2020.10.001
Self Jamal Al-Zain
2021
Calculation of the reactivity feedback coefficients for the LEU fuel of the MNSR reactor using DRAGON5/DONJON5 codes.
Zain, J.A., O.E. Hajjaji and T.E. Bardouni,
Phys. Part. Nucl. Lett., | Journal Article
10.1134/S154747712106011X
Self Jamal Al-Zain
2021
Neutronic and burn-up calculations of the (ThO2-UO2) pin cell benchmark using DRAGON5 and MCNP6.2 codes with ENDF/B-VIII.0 nuclear data library.
Zain, J.A., O.E. Hajjaji, T.E. Bardouni, M. Lahdour and T.E. Ghalbzouri,
Int. J. Energy Res., | Journal Article
10.1002/er.6460
Self Jamal Al-Zain
2021
Analysis of the reactivity coefficients and fuel burnup for MNSR research reactor using DRAGON5/DONJON5 codes.
Zain, J.A., O.E. Hajjaji, T.E. Bardouni and A.E. Mtili,
Radiat. Phys. Chem., | Journal Article
10.1016/j.radphyschem.2019.03.006
Self Jamal Al-Zain
2019
Validation of GAMOS code based on Geant4 Monte Carlo for a 12 MV Saturne43 Linac.
Zain, J.A., T.E. Bardouni, M. Mohammed and O.E. Hajjaji,
J. King Saud Uni. Sci., | Journal Article
10.1016/j.jksus.2018.07.003
Self Jamal Al-Zain
2019
Neutronic study of fuel depletion for the MNSR research reactor using DRAGON5 code.
Zain, J.A., O.E. Hajjaji and T.E. Bardouni,
Moscow Uni. Phys. Bull., | Journal Article
10.3103/s0027134919060031
Self Jamal Al-Zain
2019
Coupling of neutronics and thermal-hydraulic codes for simulation of the MNSR reactor.
Zain, J.A., O.E. Hajjaji, T.E. Bardouni and Y. Boulaich,
Nucl. Sci. Eng., | Journal Article
10.1080/00295639.2019.1622927
Self Jamal Al-Zain
2019
Analysis of depletion and inventory of the fuel for the MNSR research reactor using the deterministic code DRAGON5.
Zain, J.A., O.E. Hajjaji, T.E. Bardouni and M. Lahdour,
Nucl. Technol., | Journal Article
10.1080/00295450.2019.1662669
Self Jamal Al-Zain
2019
Validation of BEAMnrc monte carlo model for a 12 MV photon beam.
Mohammed, M., T.E. Bardouni, E. Chakir, M. Saeed, A.Z. Jamal and L. Mohamed,
J. King Saud Univ. Sci., | Journal Article
10.1016/j.jksus.2017.07.001
Self Jamal Al-Zain
2018
Validation of DRAGON4/DONJON4 simulation methodology for a typical MNSR by calculating reactivity feedback coefficient and neutron flux.
Zain, J.A., O.E. Hajjaji, T.E. Bardouni, H. Boukhal and O. Jaï,
Results Phys., | Journal Article
10.1016/j.rinp.2018.04.033
Self Jamal Al-Zain
2018
Deterministic evaluation of safety parameters and neutron flux spectra in the MNSR research reactor using DRAGON-4 code.
Zain, J.A., O.E. Hajjaji, T.E. Bardouni and H. Boukhal,
J. Radiat. Res. Applied Sci., | Journal Article
10.1016/j.jrras.2018.04.002
Self Jamal Al-Zain
2018
Calculation of the activity inventory for the MNSR reactor using DRAGON4 code.
Zain, J.A., O.E. Hajjaji and T.E. Bardouni,
Radiat. Phys. Chem., | Journal Article
10.1016/j.radphyschem.2018.06.010
Self Jamal Al-Zain
2018