Author

Djahid Lababsa

Observed names: D. Lababsa, Djahid LABABSA

Institution: Centre de Recherche Nucléaire d’Alger

Observed institutions: University of Sciences and Technology Houari Boumediene, Centre de Recherche Nucléaire d’Alger

OpenAlex ID: A5087499925

Analysis of a loss-of-flow accident resulting from the primary pump shaft break transient of the NUR research reactor

2018 · Mohammed Azzoune, Ali Boumedien, et al. · Journal of Nuclear Science and Technology · 21

Assessment of the safety impact caused by the variations of the critical position of control rods and by the presence of an in-core flux trap on the power peaking factors in an MTR-type research reactor

2023 · Hakim Mazrou, Djahid Lababsa, et al. · Nuclear Engineering and Design · 10

Performance evaluation and validation of OpenMC code for criticality analysis of an MTR-type research reactor

2024 · Djahid Lababsa, Hakim Mazrou, et al. · Annals of Nuclear Energy · 7

Cross-Verification and validation of steady-state OPAL research reactor neutronic models using OpenMC and MCNP5 Codes: A foundation for advanced coupled simulations

2025 · Djahid Lababsa, Hakim Mazrou, et al. · Annals of Nuclear Energy · 6

Software-Based automation of burnup calculations for the NUR research reactor using SCALE/TRITON T6-DEPL sequence

2024 · Djahid Lababsa, Hakim Mazrou, et al. · Annals of Nuclear Energy · 3

A Monte Carlo-based two-step neutronic‒thermal-hydraulic coupling framework for steady-state and transient analysis of the OPAL research reactor

2026 · Hakim Mazrou, Djahid Lababsa, et al. · Annals of Nuclear Energy · 1

Analysis of a flow blockage accident in a plate-type fuel assembly using MCNP5 and RELAP5 codes at NUR nuclear research reactor

2025 · M. Azzoune, K. Sidi-Ali, et al. · Annals of Nuclear Energy · 1

A Complete Comparative Study of Openmc and Mcnp5 Codes for the Criticality Analysis of Mtr-Type Research Reactors

2024 · Djahid LABABSA, Hakim MAZROU, et al. · SSRN Electronic Journal · 1

Thermal neutron flux measurement and Monte Carlo simulation using self powered neutron detector rhodium type at in-core locations of MTR nuclear research reactor

2026 · F. Adda, C. Larbes, et al. · Annals of Nuclear Energy

Assessing the impact of modeling assumptions on steady-state thermal-hydraulic safety margins in research reactors: The OPAL case

2026 · Djalal Hamed, Hakim Mazrou, et al. · Progress in Nuclear Energy

Works count: 10

Citation count: 50

H-index: 4

I10-index: 2