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Tewfik Hamidouche

Observed names: Hamidouche T., Hamidouche, Tewfik, T. Hamidouche
ORCID: 0000-0002-6406-0040
Observed ORCID: 0000-0002-6406-0040
OpenAlex ID: A5082662923
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
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
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
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
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
Total loss of flow benchmark in CIRCE-HERO integral test facility
2021 · P. Lorusso, A. Del Nevo, et al. · Nuclear Engineering and Design · 21
Analysis of loss of coolant accident in MTR pool type research reactor
2011 · Tewfik Hamidouche, El-Khider Si-Ahmed · Progress in Nuclear Energy · 19
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
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
Assessment of RELAP5 model for the University of Massachusetts Lowell Research Reactor
2006 · Anis Bousbia-Salah, Areeya Jirapongmed, et al. · Nuclear Technology and Radiation Protection · 11
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Accident Analysis in Research Reactors
2007 · M. Adorni, A Bousbia Salah, et al. · Electronic Theses and Dissertations Repository (University of Pisa) · 9
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H2020 MYRTE CIRCE-HERO experimental campaign: Post-test activity and code validation
2019 · D. Castelliti, Tewfik Hamidouche, et al. · 7
RETRAC: A Program for the Analysis of Materials Test Reactors
1994 · B. Baggoura, T. Hamidouche, et al. · Nuclear Science and Engineering · 6
Comparison of MYRRHA RELAP5 MOD 3.3 and RELAP5-3D Models on Steady State and PLOF Transient
2015 · D. Castelliti, T. Hamidouche · Nuclear Technology · 5
Application of best-estimate thermal-hydraulic codes for the safety analysis of research reactors
2006 · M. Adorni, A Bousbia Salah, et al. · 4
Numerical Analysis and Codes Qualification Based on SIRIO Experiments Within the PIACE Project
2023 · P. Lorusso, M. Tarantino, et al. · International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH) · 3
RELAP5-3D System Thermal-Hydraulics Code Adequacy for MYRRHA Safety Analyses
2026 · Tewfik Hamidouche, Rafaël Fernandez · Nuclear Technology · 2
Development of a conservative safety demonstration for loss of forced flow events in MYRRHA
2024 · Tewfik Hamidouche, Guy Scheveneels, et al. · Annals of Nuclear Energy · 1
Analysis of typical transients in the generic 10 MW IAEA Research Reactor by Relap5/3.2
2004 · A Bousbia Salah, Tewfik Hamidouche, et al. · 1
Natural circulation cooling and safety features in engineering and industrial applications, Book ‘Insights into Natural Circulation, Phenomena, Models and Issues
2010 · A Bousbia Salah, Francesco Saverio D'Auria, et al. · CINECA IRIS Institutial research information system (University of Pisa)
Numerical Investigation for Predicting the Onset of Flow Instability Under Research Reactor’s Condition
2009 · Nouara Rassoul, El-Khider Si-Ahmed, et al. · International Symposium on Convective Heat and Mass Transfer (CONV)
Analysis of Rod Ejection Accident in a Research Reactor by the Coupled Technique
2009 · Tewfik Hamidouche, El Khider Si-Ahmed, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE)
Investigation of Excursion Instability in Forced Convection in a Vertical Heated Channel
2008 · Ibrahim Rassoul, E-K. Si Ahmed, et al. · International Symposium on Advances in Computational Heat Transfer (CHT)
Works count: 35
Citation count: 437
H-index: 11
I10-index: 12
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