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Anis Bousbia Salah

Observed names: A Bousbia Salah, A Bousbia-Salah, A. Bousbia Salah, A. Bousbia-Salah, Anis Bousbia-Salah, Anis Bousbia-salah, Bousbia Salah Anis, Bousbia Salah, Anis, Bousbia-Salah A., Salah Bousbia
ORCID: 0000-0002-0556-3393
Observed ORCID: 0000-0002-0556-3393
OpenAlex ID: A5068907485
Dynamic calculations of the IAEA safety MTR research reactor Benchmark problem using RELAP5/3.2 code
2004 · Tewfik Hamidouche, Anis Bousbia-Salah, et al. · Annals of Nuclear Energy · 91
State of the Art in Using Best Estimate Calculation Tools in Nuclear Technology
2006 · TAB Francesco DAuriaUniversity of Pisa, A Bousbia Salah, et al. · CINECA IRIS Institutial research information system (University of Pisa) · 66
Analysis of partial and total flow blockage of a single fuel assembly of an MTR research reactor core
2005 · Martina Adorni, Anis Bousbia-Salah, et al. · Annals of Nuclear Energy · 65
A model for the analysis of pump start-up transients in Tehran Research Reactor
2007 · Kazem Farhadi, Anis Bousbia-salah, et al. · Progress in Nuclear Energy · 58
RELAP5/3.2 assessment against low pressure onset of flow instability in parallel heated channels
2006 · Tewfik Hamidouche, Anis Bousbia-salah · Annals of Nuclear Energy · 47
Use of coupled code technique for Best Estimate safety analysis of nuclear power plants
2006 · Anis Bousbia-Salah, Francesco D'Auria · Progress in Nuclear Energy · 37
Overview of accident analysis in nuclear research reactors
2008 · Tewfik Hamidouche, Anis Bousbia-Salah, et al. · Progress in Nuclear Energy · 36
Analysis of the IAEA research reactor benchmark problem by the RETRAC-PC code
2005 · Anis Bousbia-Salah, Tewfik Hamidouche · Nuclear Engineering and Design · 32
Neutron flux optimization in irradiation channels at NUR research reactor
2006 · B. Meftah, T. Zidi, et al. · Annals of Nuclear Energy · 31
Application of coupled code technique to a safety analysis of a standard MTR research reactor
2009 · Tewfik Hamidouche, Anis Bousbia-Salah, et al. · Nuclear Engineering and Design · 30
Analysis of the Peach Bottom Turbine Trip 2 Experiment by Coupled RELAP5-PARCS Three-Dimensional Codes
2004 · Anis Bousbia-Salah, Juswald Vedovi, et al. · Nuclear Science and Engineering · 25
Flow field assessment under a plunging liquid jet
2012 · Faiza Zidouni Kendil, Dana V. Danciu, et al. · Progress in Nuclear Energy · 20
Assessment of RELAP5 point kinetic model against reactivity insertion transient in the IAEA 10 MW MTR research reactor
2009 · T. Hamidouche, A. Bousbia-Salah · Nuclear Engineering and Design · 18
Simplified numerical model for defining Ledinegg flow instability margins in MTR research reactor
2008 · Tewfik Hamidouche, Nouara Rassoul, et al. · Progress in Nuclear Energy · 17
Analysis of the VVER1000 coolant trip benchmark using the coupled RELAP5/PARCS code
2006 · Anis Bousbia Salah, Juswald Vedovi, et al. · Progress in Nuclear Energy · 17
Uncertainty and sensitivity analyses of the Kozloduy pump trip test using coupled thermal–hydraulic 3D kinetics code
2006 · Anis Bousbia Salah, Soeren Kliem, et al. · Nuclear Engineering and Design · 17
MTR benchmark static calculations with MCNP5 code
2007 · Anis Bousbia-Salah, Hocine Benkharfia, et al. · Annals of Nuclear Energy · 16
Assessment of the CATHARE 3D capabilities in predicting the temperature mixing under asymmetric buoyant driven flow conditions
2013 · Anis Bousbia Salah, Jacques Vlassenbroeck · Nuclear Engineering and Design · 15
Numerical study of a bubble plume generated by bubble entrainment from an impinging jet
2011 · Faiza Zidouni Kendil, Eckhard Krepper, et al. · Nuclear Engineering and Design · 15
Comparative study of CFD and 3D thermal-hydraulic system codes in predicting natural convection and thermal stratification phenomena in an experimental facility
2023 · Audrius Graževičius, Anis Bousbia-Salah · Nuclear Engineering and Technology · 14
Assessment of three turbulence model performances in predicting water jet flow plunging into a liquid pool
2010 · Kendil Zidouni, Salah Bousbia, et al. · Nuclear Technology and Radiation Protection · 14
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Nuclear Energy and sustainable Development
2001 · A Bousbia Salah, Antonio Nigro, et al. · 13
Assessment of boiler tubes overheating mechanisms during a postulated loss of feedwater accident
2008 · A. Rahmani, T. Bouchami, et al. · Applied Thermal Engineering · 12
A model for the analysis of loss of decay heat removal during loss of coolant accident in MTR pool type research reactors
2006 · Anis Bousbia-salah, Brahim Meftah, et al. · Annals of Nuclear Energy · 12
Neutronics/Thermal-hydraulics Coupling in LWR Technology – CRISSUE-S WP2: State-of-the-Art Report
2004 · Francesco Saverio D'Auria, A Bousbia Salah, et al. · CINECA IRIS Institutial research information system (University of Pisa) · 12
Works count: 95
Citation count: 940
H-index: 16
I10-index: 32
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