Yahya A Alzahrani

Neutronic Analysis of SMART Reactor Core for (U-Th)O-2 and MOX Fuel Hybrid Configurations

Mehboob, K., Al-Zahrani, Y. A., Alhusawai, A., & Ali, M. (2023, January 2). ARABIAN JOURNAL FOR SCIENCE AND ENGINEERING, Vol. 1.

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.

Analysis of SMART reactor core with uranium mononitride for prolonged fuel cycle using OpenMC

Kerntechnik, 87(1), 82–90.

Analysis of activated colloidal crud in advanced and modular reactor under pump coastdown with kinetic corrosion

NUCLEAR ENGINEERING AND TECHNOLOGY, 54(12), 4571–4584.

Analysis of Doppler reactivity of SMART reactor core for hybrid fuel configurations of UO₂, MOX and (Th/U)O₂ using OpenMC

Kerntechnik, 86(3), 229–235.

Neutronic performance of fully ceramic microencapsulated of uranium oxycarbide and uranium nitride composite fuel in SMR

Annals of Nuclear Energy, 155, 108152.

Primary coolant activity of 54Mn, 59Fe, 58Co, 60Co, and 51Cr in system integrated small and modular reactor

Annals of Nuclear Energy, 160, 108356.

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.

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.

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.