NUR research reactor safety analysis study for long time natural convection (NC) operation mode

Dynamic calculations of the IAEA safety MTR research reactor Benchmark problem using RELAP5/3.2 code

Tewfik Hamidouche, A Bousbia Salah, Martina Adorni et al. · Annals of Nuclear Energy · 2004 · 84 citations

Engineering, Dynamic Calculations, Nuclear Safety +8

Analysis of partial and total flow blockage of a single fuel assembly of an MTR research reactor core

Martina Adorni, A Bousbia Salah, Tewfik Hamidouche et al. · Annals of Nuclear Energy · 2005 · 61 citations

Engineering, Civil Engineering, Reactor Safety +4

Loss of coolant accident analyses on Tehran research reactor by RELAP5/MOD3.2 code

Afshin Hedayat, Hadi Davilu, Jalil Jafari · Progress in Nuclear Energy · 2007 · 56 citations

Engineering, Nuclear Safety, Reactor Safety +4

Overview of accident analysis in nuclear research reactors

Tewfik Hamidouche, A Bousbia Salah, El‐Khider Si‐Ahmed et al. · Progress in Nuclear Energy · 2008 · 34 citations

Reliability, Nuclear Research Reactors, Engineering +6

Neutron flux optimization in irradiation channels at NUR research reactor

B. Meftah, Tahar Zidi, A Bousbia Salah · Annals of Nuclear Energy · 2006 · 28 citations

Engineering, Nuclear Safety, Neutron Source +4