Get started
Author

Djillali Saad

Observed names: D. Saad, Djillali SAAD
ORCID: 0000-0003-1482-7634
Observed ORCID: 0000-0003-1482-7634
OpenAlex ID: A5032997751
Displacement damage cross section and mechanical properties calculation of an Es-Salam research reactor aluminum vessel
2017 · Djillali Saad, Hocine Benkharfia, et al. · Nuclear Science and Techniques · 18
Calculation of SIFs for semi-elliptical surface cracks in U-shaped bellows expansion joints of Es-Salam research reactor vessel
2020 · Djillali Saad, Gintautas Dundulis, et al. · Engineering Failure Analysis · 9
Pellet-cladding mechanical interaction analysis of heavy water fuel rods under power ramps
2021 · Djillali Saad, Hocine Benkharfia, et al. · Annals of Nuclear Energy · 8
Numerical simulation of SIF in Es-Salam research reactor vessel
2018 · Djillali Saad, Gintautas Dundulis, et al. · Engineering Failure Analysis · 6
Neutron-induced damage simulations using MCNP6 and SRIM codes: Beyond neutron transmutation doping of silicon
2023 · Nadjet Osmani, H. Benkharfia, et al. · Annals of Nuclear Energy · 5
Flow blockage accident analysis in a multi purposes research reactor using Relap5 system code
2023 · Amina Lyria Deghal Cheridi, Amel Dadda, et al. · Progress in Nuclear Energy · 3
Safety analysis of the NuScale Small Modular Reactor: steady-state qualification and small break loss of coolant accident simulation using RELAP5/SCDAPSIM3.4
2026 · Ahmed HADJAM, Djillali SAAD, et al. · Radiation Protection Dosimetry · 1
PCMI Uncertainty and Sensitivity Analysis of Es-Salam Reactor Fuel Rods During Steady-State Operations
2024 · Djillali Saad, Mohamed Elhadi Boulheouchat, et al. · Nuclear Technology · 1
Numerical simulations of a creep rupture damage in Surry PWR primary circuit under TMLB accident
2020 · Djillali Saad, Ahmed Hadjam, et al. · SN Applied Sciences · 1
PDF
Mesh Size Sensitivity of the Simple Cheap Vessel Benchmark Problem
2019 · Djillali Saad, Ahmed Hadjam · Journal of Nuclear Energy Science & Power Generation Technology · 1
Uncertainty and Sensitivity Analysis of a LBLOCA Transient in the CALLISTO Test Facility Using a Statistical Approach
2026 · Ahmed Hadjam, Djillali Saad, et al. · Nuclear Technology
PCT and PCMI Uncertainty and Sensitivity Analysis of HWRR Fuel Rod During Limiting RIA
2025 · Djillali Saad, Amina Lyria Deghal Cheridi, et al. · Nuclear Technology
Works count: 12
Citation count: 53
H-index: 5
I10-index: 1
Year
Topic
Type