Dr. Jamal Al-Zain | Radiation Physics | Editorial Board Member

Published on by Chemistry Awards

Dr. Jamal  Al-Zain | Radiation Physics | Editorial Board Member

Assistant Professor | Sana’a University | Yemen

Dr. Jamal Al-Zain is a nuclear and radiation physicist whose work advances computational modeling, reactor physics, and radiation transport systems with a strong focus on thermodynamics and nuclear research reactor optimization. His contributions bridge theoretical physics with applied nuclear engineering, particularly in developing high-precision numerical models, Monte Carlo transport simulations, and thermal-hydraulic analysis frameworks that enhance reactor safety, fuel performance, and neutron behavior prediction. Dr. Al-Zain is recognized for shaping modern methodologies in simulating TRIGA Mark II and MNSR research reactors, integrating advanced tools such as OpenMC, MCNP6.2, and custom-built computational systems to improve the reliability of nuclear data and reactor operational strategies. His research further extends to innovative nuclear fuel concepts, including the utilization of transuranic nuclides for sustainable reactor designs, and the development of open-source computational tools such as ERSN-OpenMC-Py, which expands accessibility to Monte Carlo transport calculations. With a strong record of peer-reviewed publications and extensive review activity for major nuclear engineering journals, he continues to influence global research directions in reactor modeling, decommissioning analysis, and multiphysics simulation. According to Scopus metrics, Dr. Al-Zain has accumulated 102 citations from 79 documents, supported by 23 indexed publications and an h-index of 7, reflecting both the quality and impact of his work in the nuclear science community. His contributions demonstrate a commitment to improving nuclear safety, computational accuracy, and sustainable energy technologies through rigorous theoretical development and practical computational innovation.

Profiles : Scopus | Orcid 

Featured Publications :

  • El Maliki El Hlaibi, S., El Bardouni, T., Boulaich, Y., Nacir, B., El Hajjaji, O., Lahdour, M., Al-Zain, J., Ziani, H., & El Yaakoubi, H. (2025). Activity inventory of activated materials in distant components of the CENM TRIGA MARK II reactor for decommissioning planning. Progress in Nuclear Energy.

  • Mira, M., El Hajjaji, O., El Berdouni, T., Satti, H., El Bakkari, B., Al-Zain, J., Idrissi, A., & Benkabdi, C. E. (2025). Development, validation, and comparison of an OpenMC-based transport-depletion model for the Moroccan TRIGA Mark II with MCNP6.2. Nuclear Technology.

  • Lahdour, M., El Bardouni, T., El Hajjaji, O., El Bakkali, J., Al-Zain, J., Oulad-Belayachi, S., Ziani, H., Idrissi, A., & El Maliki El Hlaibi, S. (2024). ERSN-OpenMC-Py: A python-based open-source software for OpenMC Monte Carlo code. Computer Physics Communications.

  • Al-Zain, J., El Hajjaji, O., El Bardouni, T., Basfar, A. A., Alnaser, I. A., Lahdour, M., Galahom, A. A., Boulaich, Y., Ahmed, A., & Mira, M. (2024). Development and implementation of a numerical simulation system for analyzing the thermal-hydraulic (T-H) characteristics of the MNSR research reactor fuel assembly. Nuclear Engineering and Design.

  • Mira, M., El Hajjaji, O., El Bardouni, T., Al-Zain, J., & Oulad-Belayachi, S. (2023). Innovative and advanced fuel based on nuclear waste transuranic nuclides: An alternative fuel for TRIGA Mark II research reactor. Annals of Nuclear Energy.