Moustafa Aziz

Analysis of thorium fuel feasibility in large scale gas cooled fast reactor using MCNPX code

Amr Ibrahim, Moustafa Aziz, S. U. El‐Kameesy et al. · Annals of Nuclear Energy · 2017 · 24 citations

Mcnpx Code, Engineering, Energy Efficiency +7

Burnup analysis for HTR-10 reactor core loaded with uranium and thorium oxide

Mohamed A. Alzamly, Moustafa Aziz, Alya Badawi et al. · Nuclear Engineering and Technology · 2019 · 17 citations · Full text

Engineering, Nuclear Fuel Burnup, Nuclear Physics +14

Comparative analysis between homogeneous and heterogeneous models of gas cooled fast reactor core (GFR-2400)

Amr Ibrahim, Moustafa Aziz, S.A. El-Fiki et al. · Kerntechnik · 2022 · 16 citations

Mcnpx Code, Gfr-2400 Core, Engineering +14

The effect of homogenization on the neutronic parameters and transmutation of GFR-2400 fast reactor fuel assembly

Amr Ibrahim, Moustafa Aziz, S.A. El-Fiki et al. · Annals of Nuclear Energy · 2017 · 15 citations

Materials Science, Engineering, Nuclear Engineering +3

Searching for optimal accident tolerant fuel for the VVER-1200 reactor from the neutronic point of view

A. Abdelghafar Galahom, Ehab M. Aboelyazid, S.A. El-Fiki et al. · Energy Sources Part A Recovery Utilization and Environmental Effects · 2023 · 15 citations

Engineering, Nuclear Physics, Reactor Design +23