Amr Ibrahim

Integrated analysis to investigate the viability of using Thorium-based fuel instead of traditional fuel in CANDU reactor

A. Abdelghafar Galahom, Amr Ibrahim · Nuclear Engineering and Design · 2022 · 35 citations

Fuel Cycle, Thorium-based Fuel, Nuclear Fuel Burnup +11

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

Development of a discrete Reissner–Mindlin element on Winkler foundation

Jamal A. Abdalla, Amr Ibrahim · Finite Elements in Analysis and Design · 2006 · 23 citations

Mechanical Engineering, Material Property, Winkler Foundation

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