قاسم خطاب غير موثق

الانتماء الحالي في Scopus: Atomic Energy Commission of Syria

الأبحاث والمنشورات

• 2020
  MNSR transient analysis using the RELAP5/Mod3.2 code لم تثبت الفهرسة
• 2019
  Feasibility study for production of 99Mo and 99mTc by the neutron activation of 98Mo in the MNSR reactor لم تثبت الفهرسة
• 2018
  Calculation of fuel burnup and radionuclide inventory for the HEU and potential LEU fuels in the IRT research reactor لم تثبت الفهرسة
• 2017
  Radioactivity and decay heat analysis of the MNSR with HEU and LEU fuels using the GETERA code لم تثبت الفهرسة
• 2016
  Calculation of fuel burnup and radioactive inventory in the CANDU reactor using the GETERA and MCNP4C codes لم تثبت الفهرسة
• 2016
  Reactivity temperature coefficients for the HEU and LEU fuel of the MNSR reactor لم تثبت الفهرسة
• 2016
  Extending the maximum operation time of the MNSR reactor لم تثبت الفهرسة
• 2015
  Neutronic analysis for core conversion (HEU-LEU) of the low power research reactor using the MCNP4C code لم تثبت الفهرسة
• 2015
  Calculation of fuel burnup and radionuclide inventory in the 10 MW MTR type research reactor using the GETERA code لم تثبت الفهرسة
• 2015
  Investigation of BeO as a reflector for the low power research reactor لم تثبت الفهرسة
• 2015
  Study the effects of different reflector types on the neutronic parameters of the 10 MW MTR reactor using the MCNP4C code لم تثبت الفهرسة
• 2015
  Calculation and comparison of xenon and samarium reactivities of the HEU, LEU core in the low power research reactor لم تثبت الفهرسة
• 2015
  A comparative study of the neutron flux spectra in the MNSR irradiation sites for the HEU and LEU cores using the MCNP4C code لم تثبت الفهرسة
• 2014
  Determination of the LEU core safety parameters of the MNSR reactor using the MCNP4C code لم تثبت الفهرسة
• 2013
  Dose mapping simulation using the MCNP code for the Syrian gamma irradiation facility and benchmarking لم تثبت الفهرسة
• 2012
  Feedback reactivity coefficients for the Syrian MNSR research reactor لم تثبت الفهرسة
• 2011
  Monte Carlo simulation of core physics parameters of the Syrian MNSR reactor لم تثبت الفهرسة
• 2011
  Calculation of fuel burnup and radionuclide inventory in the Syrian miniature neutron source reactor using the GETERA code لم تثبت الفهرسة
• 2011
  Calculation of the power distribution in the fuel rods of the low power research reactor using the MCNP4C code لم تثبت الفهرسة
• 2010
  Calculation and comparison of the neutron energy flux spectra in the Syrian MNSR irradiation sites using the MCNP-4C code لم تثبت الفهرسة
• 2009
  Four energy group neutron flux distributions in the Syrian Miniature Neutron Source Reactor using the WIMSD4 and CITATION codes لم تثبت الفهرسة
• 2009
  Calculations of the thermal and fast neutron fluxes in the Syrian miniature neutron source reactor using the MCNP-4C code لم تثبت الفهرسة
• 2009
  Assessment of fuel conversion from HEU to LEU in the Syrian MNSR reactor using the MCNP code لم تثبت الفهرسة
• 2008
  Design of a permanent Cd-shielded epithermal neutron irradiation site in the Syrian Miniature Neutron Source Reactor لم تثبت الفهرسة
• 2007
  Measurement of the fast neutron flux in the MNSR inner irradiation site لم تثبت الفهرسة
• 2007
  Estimating the four-factor product (ε p Pfnl P tnl) for the accurate calculation of xenon and samarium reactivities in the Syrian Miniature Neutron Source Reactor لم تثبت الفهرسة
• 2007
  Sensitivity analysis of reflector types and impurities in 10 MW MTR type nuclear research reactor لم تثبت الفهرسة
• 2007
  Determination of the axial thermal neutron flux non-uniform factor in the MNSR inner irradiation capsule لم تثبت الفهرسة
• 2006
  The effect of temperature and control rod position on the spatial neutron flux distribution in the Syrian miniature neutron source reactor لم تثبت الفهرسة
• 2005
  Calculations of fuel burn-up and radionuclide inventory in the syrian miniature neutron source reactor using the WIMSD4 code لم تثبت الفهرسة
• 2004
  Calculation of the top beryllium shim plate worths for the syrian miniature neutron source reactor لم تثبت الفهرسة
• 2000
  Neutronics-design modification of the Syrian miniature neutron source reactor لم تثبت الفهرسة
• 1999
  Lowering the enrichment of the Syrian miniature neutron source reactor لم تثبت الفهرسة
• 1999
  Reactivity-flooding effect of the MNSR inner irradiation sites لم تثبت الفهرسة
• 1997
  The generalized PN synthetic acceleration method for linear transport problems with highly anisotropic scattering لم تثبت الفهرسة