Yahya Abdullah M Alzahrani

Addressing Uncertainties Across All Design Stages of Advanced Reactors Development

Advanced Reactor Safety (ARS), 268–277.

Primary Site Selection for Air Freight Transport of Department of Defense Microreactors

Advanced Reactor Safety (ARS), 176–183.

Quantification of In-Containment Mechanistic Source Term for Advanced Light Water Reactor

Advanced Reactor Safety (ARS), 4–15.

A Limited-Scope Probabilistic Risk Assessment Study to Risk-Inform the Design of a Fuel Storage System for Spent Pebble-Filled Dry Casks

ENG, 4(2), 1655–1683.

Characterization of Dynamic Behaviors in Licensee Event Report Data to Support PRA

18th International Probabilistic Safety Assessment and Analysis (PSA 2023), 334–343.

Creating Annotated Corpus and Named Entity Recognition Model for Nuclear Power Industry

18th International Probabilistic Safety Assessment and Analysis (PSA 2023), 262–271.

Leveraging Probabilistic Risk Assessment and Machine Learning for Safety and Cost Optimization in HAZMAT Transportation

Volume 13: Research Posters; Safety Engineering, Risk and Reliability Analysis, 13.

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.

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)

Farag, A. S., Alzahrani, Y. A., & Diaconeasa, M. A. (2023, July). NUCLEAR ENGINEERING AND DESIGN, Vol. 408.

Probabilistic risk assessment approach for the transportation of micro reactors: Evaluating the impact of highway accidents on the surrounding population

Probabilistic Risk Assessment Approach for the Transportation of Micro Reactors: Evaluating the Impact of Highway Accidents on the Surrounding Population. Volume 13: Research Posters; Safety Engineering, Risk and Reliability Analysis, 13.

Probabilistic risk assessment study for uncertainty quantification of spent pebble-bed dry cask storage system operation

Probabilistic Risk Assessment Study for Uncertainty Quantification of Spent Pebble-Bed Dry Cask Storage System Operation. Volume 13: Research Posters; Safety Engineering, Risk and Reliability Analysis, 13.

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(1), 779–792.