All Stories

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

    Article • Journal of Nuclear Materials, August 2023, Elsevier

    Dr. Mohammmad Alrwashdeh

  2. 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

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

    Article • Energies, October 2022, MDPI AG

    Dr. Mohammmad Alrwashdeh

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

    Article • Energies, July 2022, MDPI AG

    Dr. Mohammmad Alrwashdeh

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

    Article • Energies, May 2022, MDPI AG

    Dr. Mohammmad Alrwashdeh

  6. 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

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

    Article • Nuclear Engineering and Design, December 2021, Elsevier

    Dr. Mohammmad Alrwashdeh

  8. 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

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

    Article • August 2020, ASME International

    Dr. Mohammmad Alrwashdeh

  10. Evaluation review of the 250Cf neutron cross section

    Article • Applied Radiation and Isotopes, December 2019, Elsevier

    Saeed Alameri, Dr. Mohammmad Alrwashdeh

  11. 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

  12. 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

  13. 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

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

    Article • January 2019, American Nuclear Society (ANS)

    Dr. Mohammmad Alrwashdeh, Dr. Ahmed K. Alkaabi

  15. 239Pu evaluation comparison study

    Article • Annals of Nuclear Energy, August 2018, Elsevier

    Dr. Mohammmad Alrwashdeh

  16. Covariance data evaluation for 233U

    Article • Applied Radiation and Isotopes, March 2018, Elsevier

    Dr. Mohammmad Alrwashdeh

  17. U233 Data Evaluation for Criticality Study

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

    Dr. Mohammmad Alrwashdeh

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

    Article • Annals of Nuclear Energy, August 2014, Elsevier

    Dr. Mohammmad Alrwashdeh

  19. 233U Evaluation Comparison Study

    Article • July 2014, ASME International

    Dr. Mohammmad Alrwashdeh

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

    Article • July 2014, ASME International

    Dr. Mohammmad Alrwashdeh

  21. Nuclear Data Statistical Treatment

    Article • July 2013, ASME International

    Dr. Mohammmad Alrwashdeh