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  1. Zubair, Muhammad, Eslam Ahmed, and Donny Hartanto. "Comparison of different glass materials to protect the operators from gamma-rays in the PET using MCNP code." Radiation Physics and Chemistry 190 (2022).
  2. Muhammad Zubair, Priyonta Rahman. “Importance Analysis of Containment Spray System in Pressurized Water Reactor (PWR)”. Book Chapter, Practical Applications in Reliability Engineering, Online ISBN: 978-1-83968-400-5. Print ISBN: 978-1-83968-399-2. pp 37-44. IntechOpen Publisher, London, United Kingdom. 2021.
  3. Adnan Raza Khan, Yu Shengfu, Muhammad Zubair. “Direct observation of austenite and pearlite formation in thermally simulated Coarse Grain Heat-Affected Zone of pearlite railway steel”. Journal of Materials Engineering and Performance. Volume 30, Issue 1, pp 497-509, 2021.
  4.   M. Mustafa Azeem, Di Yun, Muhammad Zubair. “Atomic insights on interaction mechanism of dislocation with void/impurity/ precipitates in BCC Iron”. Proceedings of the 2021, 28th International Conference on Nuclear Engineering, ICONE28. August 4-6, 2021.
  5. Muhammad  Zubair, A. Wakeel, M. Azeem, A. Tabassum. “Computational analysis of high carbon steel for optimal design”. Proceedings of 2021, 18th International Bhurban Conference on Applied Sciences & Technology (IBCAST) Islamabad, Pakistan, January 12-16, 2021.
  6. Zubair, Muhammad, Reem Rashid Al Suwaidi, and Alwaad Abdullah Al Souqi. "Behavior of Emergency Core Cooling System (ECCS) during the early stage of Loss of Coolant Accident (LOCA) for APR 1400 with Flownex software." Progress in Nuclear Energy 141 (2021): 103949.
  7. Syarif, Junaidi, Khaled Badawy, and Hussien A. Hussien. "Atomistic simulation of the diffusion behavior in Al-Fe." Nuclear Materials and Energy 29 (2021): 101073.
  8. Hartanto, D., Liem, P.H. "Sensitivity and uncertainty analyses of a high temperature gas-cooled reactor by using a 44-group covariance library". Annals of Nuclear Energy. 2021.
  9. Syarif, J., Badawy, K. "Computational modelling of cold rolling of ferritic iron containing ε-Cu precipitates". Materials Today Communications. 2021
  10. Alhammadi, S.Y., Alktebi, A.A., Eldemiery, A.E., Gillette, V., El Saj Assad, M., Alshabi, M., Khuwaileh, B.A. "An Extended Thermosyphon Cooling System for APR-1400 Reactor Design". Case Studies in Thermal Engineering. 2021
  11. Khuwaileh, B.A., Al-Shabi, M., El Haj Assad, M. "Artificial Neural Network based Particle Swarm Optimization solution approach for the inverse depletion of used nuclear fuel". Annals of Nuclear Energy. 2021
  12. Khuwaileh, Bassam A., Mohammad A. Al-Shabi, and Mamdouh El Haj Assad. "Uncertainty contribution estimation for Monte Carlo uncertainty quantification via subspace analysis: neutronics case study." Big Data III: Learning, Analytics, and Applications. Vol. 11730. International Society for Optics and Photonics, 2021.
  13. Hartanto, Donny, and Peng Hong Liem. "Neutron importance based lattice-to-core projection technique and its application for HTGR design using Monte Carlo method." Nuclear Engineering and Design 381 (2021): 111338.
  14. Alnaqbi, J., Hartanto, D., Alnuaimi, R., Imron, M., & Gillette, V.. Static and transient analyses of Advanced Power Reactor 1400 (APR1400) initial core using open-source nodal core simulator KOMODO. Nuclear Engineering and Technology (2021).
  15. Muhammad Zubair, Samar El Sayed Ahmed, Ahmad Ababneh, Abdullah Omar and Abdelrahman Mohamed. "Gamma Spectroscopy for the Investigation of Radiation Contamination in the UAE". International Journal of Nuclear Energy Science and Technology. Volume 14, Issue 2, pp 141-153, 2020.
  16. Khuwaileh, B.A., Al-Hamadi, F.I., Hartanto, D., Said, Z., Ali, M. "On the performance of nanofluids in APR 1400 PLUS7 assembly: Neutronics". Annals of Nuclear Energy. 2020.
  17. Syarif, J., Yousuf, M.H., Sajuri, Z., Merabtene, M., Omar, M.Z. "Effect of partial solution treatment temperature on microstructure and tensile properties of 440C martensitic stainless steel". Metals, 2020.
  18. Al-Hamadi, F. I., Khuwaileh, B. A., Liem, P. H., & Hartanto, D. (2020). Analysis of OECD/NEA medium 1000 MWth sodium-cooled fast reactor using the Monte Carlo serpent code and ENDF/B-VIII. 0 nuclear data library. Nuclear Science and Techniques, 31(12), 1-11.
  19. Hartanto, D., Alshamsi, A., Alsuwaidi, A., Bilkhair, A., Hukal, H. A., & Zubair, M. (2020). Neutronics Assessment of Accident-Tolerant Fuel in Advanced Power Reactor 1400 (APR1400). Atom Indonesia, 46(3), 177-186.
  20. Hartanto, D., Alhamad, S., Mahmoud, K., Kurdi, N., & Zubair, M. (2020). Neutronics design study of an advanced lead-cooled modular nuclear reactor (ALMANAR). International Journal of Nuclear Energy Science and Technology, 14(1), 1-14.