Author

M. Kaddour

Observed name: Mohamed Kaddour

Institution: Abdelmalek Essaâdi University

Observed institution: Abdelmalek Essaâdi University

OpenAlex ID: A5032206151

Monte Carlo analysis of the influence of germanium dead layer thickness on the HPGe gamma detector experimental efficiency measured by use of extended sources

2014 · E. Chham, F. Piñero García, et al. · Applied Radiation and Isotopes · 32

Sensitivity and uncertainty quantification of neutronic integral data in the TRIGA Mark II research reactor

2021 · M. Makhloul, H. Boukhal, et al. · Nuclear Engineering and Technology · 10

Monte Carlo analysis of KRITZ-2 critical benchmarks on the reactivity temperature coefficient using ENDF/B-VII.1 and JENDL-4.0 nuclear data libraries

2015 · S. El Ouahdani, H. Boukhal, et al. · Annals of Nuclear Energy · 9

235U elastic cross-section adjustment in criticality benchmarks – Comparison between JENDL-4.0 and ENDF/-VII.1

2018 · M. Makhloul, H. Boukhal, et al. · Annals of Nuclear Energy · 7

Adjustment of group cross sections by means of integral data (ENDF/-VII.1)

2019 · M. Makhloul, H. Boukhal, et al. · Progress in Nuclear Energy · 4

ERSN-OpenMC, a Java-based GUI for OpenMC Monte Carlo code

2015 · Jaafar EL Bakkali, Tarek EL Bardouni, et al. · Journal of Radiation Research and Applied Sciences · 4

56Fe, 16O, 1H Elastic and capture cross sections analysis in PCA-REPLICA benchmark

2021 · M. Kaddour, T. El Bardouni, et al. · Progress in Nuclear Energy · 3

Sensitivity and Uncertainty Quantification of Neutronic Integral Data Using ENDF/B-VII.1 and JENDL-4.0 Evaluations

2020 · Mustapha Makhloul, H. Boukhal, et al. · IntechOpen eBooks · 2

235U capture cross-section adjustment in criticality benchmarks using ENDF/B-VII.1 evaluation

2019 · M. Makhloul, H. Boukhal, et al. · Journal of Radiation Research and Applied Sciences · 2

ENDF/B-VII.0, JEFF-3.1 and JENDL-4 Iron and Water Cross Sections Analysis Using the PCA-REPLICA Shielding

2014 · O. Allaoui, T.El Bardouni, et al. · Universal Journal of Physics and Application · 2

Sensitivity and Uncertainty Analysis of the Keff Due to ENDF/B-VII.0 Cross Sections Uncertainties of the Major Isotopes in Nuclear Reactors

2013 · M. Kaddour, T. El Bardouni, et al. · Advances in Energy and Power · 2

Sensitivity and Uncertainty Analysis on the Keff Produced by the 1H, 16O, 239Pu and 240Pu Cross Sections Uncertainties

2017 · Abdulaziz Ahmed, H. Boukhal, et al. · Universal Journal of Physics and Application

Works count: 12

Citation count: 77

H-index: 4

I10-index: 2