All Stories

  1. Nuclear reactor cladding enhancement via DES electrodeposition: Electrochemical kinetics and surface architecture of Cr-coated Zr-4 claddings

    Article • Annals of Nuclear Energy, February 2026, Elsevier

    Saeed Alameri, Dr. Mohammmad Alrwashdeh

  2. Benchmarking SiC f /SiC, FeCrAl, and Cr-coated Zr alloy claddings: evaluating thermomechanical properties and high-temperature oxidation resistance of next-generation nuclear claddings

    Article • Advances in Physics X, September 2025, Taylor & Francis

    Dr. Mohammmad Alrwashdeh

  3. Excess reactivity control using innovative burnable absorber configuration for a 24-month cycle APR-1400

    Article • Alexandria Engineering Journal, September 2025, Elsevier

    Saeed Alameri, Dr. Mohammmad Alrwashdeh

  4. Performance Analysis of an Enhanced Cr-Coated Fuel Cladding System

    Article • Nuclear Technology, April 2025, Taylor & Francis

    Saeed Alameri, Dr. Mohammmad Alrwashdeh

  5. Impact of in-core fuel management on the radial peaking factor in the APR-1400 with accident-tolerance fuel cladding

    Article • Nuclear Engineering and Technology, April 2025, Elsevier

    Saeed Alameri, Dr. Mohammmad Alrwashdeh

  6. Critical evaluation of accident tolerant fuel selection criteria for APR-1400 nuclear reactors

    Article • Advances in Physics X, January 2025, Taylor & Francis

    Dr. Mohammmad Alrwashdeh

  7. Unveiling the latest progresses in chromium-coated Zircaloy cladding ATF materials: Fabrication techniques, performance metrics, and beyond

    Article • Alexandria Engineering Journal, December 2024, Elsevier

    Dr. Mohammmad Alrwashdeh

  8. Data and modeling sensitivity analysis for molten salt fast reactor benchmark – Static calculations

    Article • Progress in Nuclear Energy, December 2024, Elsevier

    Dr. Mohammmad Alrwashdeh

  9. Correction: Alrwashdeh, M.; Alameri, S.A. Chromium-Coated Zirconium Cladding Neutronics Impact for APR-1400 Reactor Core. Energies 2022, 15, 8008

    Article • Energies, May 2024, MDPI AG

    Saeed Alameri, Dr. Mohammmad Alrwashdeh

  10. Review of Neutron Physics Analyses for Accident-Tolerant Fuel System

    Article • Engineered Science, January 2024, Engineered Science Publisher

    Dr. Mohammmad Alrwashdeh

  11. Review of Neutronics, Thermal-Hydraulic, and Fuel Performance Research of Accident Tolerant Fuels for APR-1400 in United Arab Emirates Nuclear Power Plants

    Article • January 2024, Springer Science + Business Media

    Dr. Mohammmad Alrwashdeh

  12. Correction: A Neutronics Study of the Initial Fuel Cycle Extension in APR-1400 Reactors: Examining Homogeneous and Heterogeneous Enrichment Design

    Article • Arabian Journal for Science and Engineering, December 2023, Springer Science + Business Media

    Saeed Alameri, Dr. Mohammmad Alrwashdeh

  13. Part Strength Control Element Assemblies Effectiveness in APR1400 Reactivity Management During Transient Operation

    Article • Arabian Journal for Science and Engineering, August 2023, Springer Science + Business Media

    Saeed Alameri, Dr. Mohammmad Alrwashdeh

  14. Sensitivity neutronic analysis of accident tolerant fuel concepts in APR1400

    Article • Journal of Nuclear Materials, August 2023, Elsevier

    Dr. Mohammmad Alrwashdeh, Saeed Alameri

  15. A Neutronics Study of the Initial Fuel Cycle Extension in APR-1400 Reactors: Examining Homogeneous and Heterogeneous Enrichment Design

    Article • Arabian Journal for Science and Engineering, May 2023, Springer Science + Business Media

    Dr. Mohammmad Alrwashdeh, Saeed Alameri

  16. Chromium-Coated Zirconium Cladding Neutronics Impact for APR-1400 Reactor Core

    Article • Energies, October 2022, MDPI AG

    Dr. Mohammmad Alrwashdeh, Saeed Alameri

  17. Neutronic Analysis of SiC/SiC Sandwich Cladding Design in APR-1400 under Normal Operation Conditions

    Article • Energies, July 2022, MDPI AG

    Dr. Mohammmad Alrwashdeh, Saeed Alameri

  18. SiC and FeCrAl as Potential Cladding Materials for APR-1400 Neutronic Analysis

    Article • Energies, May 2022, MDPI AG

    Dr. Mohammmad Alrwashdeh, Saeed Alameri

  19. Preliminary three-dimensional neutronic analysis of IFBA coated TRISO fuel particles in prismatic-core advanced high temperature reactor

    Article • Annals of Nuclear Energy, December 2021, Elsevier

    Dr. Mohammmad Alrwashdeh, Saeed Alameri

  20. Preliminary neutronic analysis of alternative cladding materials for APR-1400 fuel assembly

    Article • Nuclear Engineering and Design, December 2021, Elsevier

    Dr. Mohammmad Alrwashdeh, Saeed Alameri

  21. CONSOLIDATION OF REACTOR PHYSICS EDUCATION – THE KHALIFA UNIVERSITY STUDENT FIELD TRIPS CASE STUDY

    Article • EPJ Web of Conferences, January 2021, EDP Sciences

    Dr. Mohammmad Alrwashdeh, Saeed Alameri

  22. Two-Dimensional Full Core Analysis of IFBA-Coated TRISO Fuel Particles in Very High Temperature Reactors

    Article • August 2020, ASME International

    Dr. Mohammmad Alrwashdeh, Saeed Alameri

  23. Evaluation review of the 250Cf neutron cross section

    Article • Applied Radiation and Isotopes, December 2019, Elsevier

    Saeed Alameri, Dr. Mohammmad Alrwashdeh

  24. Preliminary Study of a Prismatic-Core Advanced High-Temperature Reactor Fuel Using Homogenization Double-Heterogeneous Method

    Article • Nuclear Science and Engineering, October 2019, Taylor & Francis

    Dr. Mohammmad Alrwashdeh, Saeed Alameri, Dr. Ahmed K. Alkaabi

  25. Reactor Monte Carlo (RMC) model validation and verification in compare with MCNP for plate-type reactor

    Article • AIP Advances, July 2019, American Institute of Physics

    mohammmad alrwashdeh, Saeed Alameri, Dr. Mohammmad Alrwashdeh

  26. Effect of Thermal Energy Storage Integration on Overall Nuclear Power Plant Efficiency

    Article • January 2019, American Nuclear Society (ANS)

    Dr. Mohammmad Alrwashdeh, Dr. Ahmed K. Alkaabi, Saeed Alameri

  27. Homogenization of TRISO Fuel Using Reactivity Equivalent Physical Transformation Method

    Article • January 2019, American Nuclear Society (ANS)

    Dr. Mohammmad Alrwashdeh, Dr. Ahmed K. Alkaabi, Saeed Alameri

  28. 239Pu evaluation comparison study

    Article • Annals of Nuclear Energy, August 2018, Elsevier

    Dr. Mohammmad Alrwashdeh

  29. Covariance data evaluation for 233U

    Article • Applied Radiation and Isotopes, March 2018, Elsevier

    Dr. Mohammmad Alrwashdeh

  30. U233 Data Evaluation for Criticality Study

    Article • Journal of Nuclear Engineering and Radiation Science, June 2016, ASME International

    Dr. Mohammmad Alrwashdeh

  31. Development of a code FITWR for nuclear cross section statistical analysis

    Article • Annals of Nuclear Energy, August 2014, Elsevier

    Dr. Mohammmad Alrwashdeh

  32. 233U Evaluation Comparison Study

    Article • July 2014, ASME International

    Dr. Mohammmad Alrwashdeh

  33. Application of Some Turbulence Models to Simulate Buoyancy-Driven Flow

    Article • July 2014, ASME International

    Dr. Mohammmad Alrwashdeh

  34. Nuclear Data Statistical Treatment

    Article • July 2013, ASME International

    Dr. Mohammmad Alrwashdeh