محمد البرهوم غير موثق

الانتماء الحالي في Scopus: Atomic Energy Commission of Syria

الأبحاث والمنشورات

• 2026
  Benchmark-based neutronic and thermal-hydraulic evaluation of a modified beryllium reflector for enhanced irradiation capability in an MTR-10 MW reactor (Scopus) جامعة دمشق
• 2026
  MOX fuel mixed with graphite as a fuel for use in Generation IV nuclear reactor using the Monte Carlo method (Scopus) جامعة دمشق
• 2024
  Molybdenum with MOX Nuclear Fuel to be Used for the Second Load of Generation IV ALLEGRO Nuclear Reactor Using the Monte Carlo Method (Scopus) جامعة دمشق
• 2021
  Optimization of the epithermal neutronic beam for BNCT at a 22 MW MTR reactor (Scopus)
• 2017
  Burning of the Minor Actinides in fuel cycle of the MTR-reactors (Scopus)
• 2017
  The use of MOX caramel fuel mixed with 241Am, 242mAm and 243Am as burnable absorber actinides for the MTR research reactors (Scopus)
• 2017
  A computational study of re-cycling the MTR research reactors with MOX fuel mixed with 241Am, 242Am and 243Am as burnable absorbers actinides using the MCNP4C code (Scopus)
• 2016
  Performance of the MTR core with MOX fuel using the MCNP4C2 code (Scopus)
• 2016
  Neutronic calculations of the MTR-22 MW research reactor loaded with MOX (PuO2&UO2) Caramel fuel using the MCNP5 Code (Scopus)
• 2016
  Study of criticality safety and neutronic parameters of UO2 fuel in MTR research reactors using the MCNP4C code (Scopus)
• 2015
  Calculation of the effect of boron as impurity on the reactivity of the Miniature Neutron Source Reactors using the MCNP code (Scopus)
• 2015
  Calculation of the effects of Eu as impurity on the reactivity of the Miniature Neutron Source Reactors using the MCNP code (Scopus)
• 2015
  Design calculation of an epithermal neutronic beam for BNCT at the Syrian MNSR using the MCNP4C code (Scopus)
• 2015
  Effects of non-metals on the reactivity of MNSRs for HEU fuel using the MCNP code (Scopus)
• 2015
  Minimizing MTR reactor uranium load with the use of MOX fuel by employing ORIGEN-S and MCNP4C codes (Scopus)
• 2012
  Calculation of the self-shielding factors for the upper reflector in MNSRs (Scopus)
• 2012
  Reactivity cost for different top reflector materials in miniature neutron source reactors (Scopus)
• 2012
  Experimental determination of the shielding characteristics of the dwelling houses’ building materials against neutrons in the Central Region of Syria (Scopus) جامعة حمص
• 2011
  Graphite reflecting characteristics and shielding factors for Miniature Neutron Source Reactors (Scopus)
• 2011
  Performance of UO2 ceramic fuel in low-power research reactors (Scopus)
• 2011
  Invariability of neutron flux in internal and external irradiation sites in MNSRs for both HEU and LEU cores (Scopus)
• 2011
  Heavy water as upper reflector in MNSRs (Scopus)
• 2011
  Thermal-hydraulic and safety aspects of UO2 fuel for low-power reactors (Scopus)
• 2011
  The use of U3Si2 dispersed fuel in low-power research reactors (Scopus)
• 2011
  Neutronic calculations of the U3Si LEU as a dispersed fuel for low-power research reactors (Scopus)
• 2011
  An experimental study of the shielding characteristics of the dwelling house building materials against gamma radiations in the Central Region of Syria (Scopus) جامعة حمص
• 2010
  Minimization of uranium load in Miniature Neutron Source Reactors (Scopus)
• 2010
  Thermalhydraulics and safety aspects of the use of monolithic U-9Mo LEU fuel in the low-power reactors (Scopus)
• 2010
  The neutronic aspects of U-9Mo as a LEU fuel for Low-power reactors (Scopus)
• 2010
  Optimization of the neutronics design of MNSRs (Scopus)
• 2010
  Thermal-hydraulics features of the use of LEU U3Si2 fuel in low-power reactors (Scopus)
• 2010
  Thermohydraulic features of the use of U3Si LEU fuel in low-power research reactors (Scopus)
• 2009
  A thermal-hydraulic code (THYD) for the miniature neutron source reactor thermal-hydraulic transients (Scopus)
• 2009
  Optimization of the reflector design of the Syrian MNSR (Scopus)
• 2008
  Automation of the modeling and some neutronic calculations of the Syrian miniature neutron source reactors (Scopus)
• 2005
  A 3-D neutronics model for the calibration of the control rod of the syrian MNSR (Scopus)
• 2004
  Extending the operable time of the Syrian MNSR (Scopus)