Yahya Alzahrani

Lee, J., Tayfur, H., Hamza, M. M., Alzahrani, Y. A., & Diaconeasa, M. A. (2023). A Limited-Scope Probabilistic Risk Assessment Study to Risk-Inform the Design of a Fuel Storage System for Spent Pebble-Filled Dry Casks. Eng. https://doi.org/10.3390/eng4020094

Mehboob, K., Al-Zahrani, Y. A., Alhusawai, A., & Ali, M. (2023, January 2). Neutronic Analysis of SMART Reactor Core for (U-Th)O-2 and MOX Fuel Hybrid Configurations. ARABIAN JOURNAL FOR SCIENCE AND ENGINEERING, Vol. 1. https://doi.org/10.1007/s13369-022-07541-7

Farag, A. S., Alzahrani, Y. A., & Diaconeasa, M. A. (2023). Pool inlet LOCA safety analysis in support of the emergency core spray system success criteria development of the PULSTAR research reactor. NUCLEAR ENGINEERING AND DESIGN, 403. https://doi.org/10.1016/j.nucengdes.2023.112163

Farag, A. S., Alzahrani, Y. A., & Diaconeasa, M. A. (2023, July). Pool inlet LOCA safety analysis in support of the emergency core spray system success criteria development of the PULSTAR research reactor (vol 403, 112163, 2023). NUCLEAR ENGINEERING AND DESIGN, Vol. 408. https://doi.org/10.1016/j.nucengdes.2023.112342

Al-Zahrani, Y. A., Mehboob, K., Alshahrani, T. F., Abolaban, F. A., & Younis, H. (2022). Analysis of SMART reactor core with uranium mononitride for prolonged fuel cycle using OpenMC. Kerntechnik, 87(1), 82–90. https://doi.org/10.1515/kern-2021-1000

Mehboob, K., & Al-Zahrani, Y. A. (2022). Analysis of activated colloidal crud in advanced and modular reactor under pump coastdown with kinetic corrosion. NUCLEAR ENGINEERING AND TECHNOLOGY, 54(12), 4571–4584. https://doi.org/10.1016/j.net.2022.08.017

Alzahrani, Y., Mehboob, K., Abolaban, F. A., & Younis, H. (2021). Analysis of Doppler reactivity of SMART reactor core for hybrid fuel configurations of UO<sub>2</sub>, MOX and (Th/U)O<sub>2</sub> using OpenMC. Kerntechnik, 86(3), 229–235. https://doi.org/10.1515/kern-2020-0063

Al-Zahrani, Y. A., Mehboob, K., Mohamad, D., Alhawsawi, A., & Abolaban, F. A. (2021). Neutronic performance of fully ceramic microencapsulated of uranium oxycarbide and uranium nitride composite fuel in SMR. Annals of Nuclear Energy, 155, 108152. https://doi.org/10.1016/j.anucene.2021.108152

Mehboob, K., Al-Zahrani, Y. A., Aljohani, M. S., & Alhawsawi, A. (2021). Primary coolant activity of 54Mn, 59Fe, 58Co, 60Co, and 51Cr in system integrated small and modular reactor. Annals of Nuclear Energy, 160, 108356. https://doi.org/10.1016/j.anucene.2021.108356

Mehboob, K., Al-Zahrani, Y. A., & Alhawsawi, A. (2021). Primary coolant source term of System-Integrated Modular Advanced Reactor (SMART) due to activated colloidal crud under dynamic grid load following. Nuclear Engineering and Design, 384, 111480. https://doi.org/10.1016/j.nucengdes.2021.111480

Mehboob, K., Al-Zahrani, Y. A., & Mohamad, D. (2021). Simulation of activated corrosion product activity in Korean design system-integrated modular advanced reactor (SMART) under steady-state flow and linearly accelerated corrosion. Progress in Nuclear Energy, 134, 103667. https://doi.org/10.1016/j.pnucene.2021.103667

Mehboob, K., Alzahrani, Y. A., Fallatah, O., Qutub, M. M. T., & Younis, H. (2020). Radioactivity and Radiation Hazard Indices Assessment for Phosphate Rock Samples from Al-Jalamid, Turaif, Umm Wu’al, and As-Sanam, Saudi Arabia. Arabian Journal for Science and Engineering, 9. https://doi.org/10.1007/s13369-020-04929-1