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An inter-comparison between ENDF/B-VIII.0-NECP-Atlas and ENDF/B-VIII.0-NJOY results for criticality safety benchmarks and benchmarks on the reactivity temperature coefficient

Nuclear Engineering and Technology, 2021, 53(8), , pp.2445-2453

2021

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Neutron beam characterization for the Moroccan TRIGA Mark II reactor

Journal of radioanalytical and nuclear chemistry, 2021-03, Vol.327 (3), p.1063-1072

2021

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Processing and benchmarking of evaluated nuclear data file/b-viii.0β4 cross-section library by analysis of a series of critical experimental benchmark using the monte carlo code MCNP(X) and NJOY2016

Nuclear Engineering and Technology, 2017, 49(8), , pp.1610-1616

2017

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Neutronic feasibility study of (Th-233U)-ZrH1.65 fuel in a modelled TRIGA research reactor

Journal of King Saud University. Science, 2022-02, Vol.34 (2), p.101769, Article 101769

2022

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Neutronic investigation of prospective dual-cooled micro-heterogeneous duplex fuel for small modular long-life reactors: Assembly level design and analysis

Progress in nuclear energy (New series), 2023-06, Vol.160, p.104680, Article 104680

2023

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Processing of JEFF-3.3 and ENDF/B-VIII.0 and testing with critical benchmark experiments and TRIGA Mark II research reactor using MCNPX

Applied radiation and isotopes, 2019-08, Vol.150, p.146-156

2019

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Revolutionizing LWR SMR reactors: exploring the potential of (Th-233U-235U)O2 fuel through a parametric study

Energy sources. Part A, Recovery, utilization, and environmental effects, 2023-10, Vol.45 (4), p.10162-10175

2023

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The use of burnable absorbers integrated into TRISO/QUADRISO particles as a reactivity control method in a pebble-bed HTR reactor fuelled with (Th,233U)O2

Nuclear engineering and design, 2021-12, Vol.384, p.111476, Article 111476

2021

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Parametric neutronic analysis of different cladding options for ThO2 pellet of advanced dual-cooled annular PWR assembly

Nuclear engineering and design, 2023-12, Vol.414, p.112533, Article 112533

2023

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Revolutionizing LWR SMR reactors: exploring the potential of (Th- 233 U- 235 U)O 2 fuel through a parametric study

Energy sources. Part A, Recovery, utilization, and environmental effects, 2023-10, Vol.45 (4), p.10162-10175

2023

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Uranium and other heavy metal sorption from Moroccan phosphoric acid with argan nutshell sawdust

Minerals engineering, 2021-09, Vol.171, p.107085, Article 107085

2021

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A comparative analysis of the neutronic performance of thorium mixed with uranium or plutonium in a high‐temperature pebble‐bed reactor

International journal of energy research, 2021-09, Vol.45 (11), p.16824-16841

2021

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Neutronic and burnup characteristics of potential dual‐cooled annular (Th‐233U‐235U)O2 fuel for the advanced pressurized water reactors: An assembly‐level analysis

International journal of energy research, 2022-12, Vol.46 (15), p.23501-23516

2022

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Neutronic investigation of the thorium-based mixed-oxide as an alternative fuel in the TRIGA Mark-II research reactor – Part I: A beginning of life calculations

Annals of nuclear energy, 2020-06, Vol.140, p.107075, Article 107075

2020

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Neutronic and burnup characteristics of potential dual‐cooled annular ( Th‐ 233 U‐ 235 U ) O 2 fuel for the advanced pressurized water reactors: An assembly‐level analysis

International journal of energy research, 2022-12, Vol.46 (15), p.23501-23516

2022

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Modeling and simulating the induced effect on the steel collimator plug used in the PGAA facility of the Moroccan TRIGA Mark-II reactor under different neutron irradiation levels

Applied radiation and isotopes, 2021-04, Vol.170, p.109620-109620, Article 109620

2021

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New open-source software for gamma-ray spectra analysis

Applied radiation and isotopes, 2022-07, Vol.185, p.110227-110227, Article 110227

2022

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An inter-comparison between ENDF/B-VIII.0-NECP-Atlas and ENDF/B-VIII.0-NJOY results for criticality safety benchmarks and benchmarks on the reactivity temperature coefficient

Nuclear engineering and technology, 2021, Vol.53 (8), p.2445-2453

2021

Volltextzugriff (PDF)

Neutronic investigation of a VVER-1200 (Th-233U)O2 fuel assembly with protactinium oxide as a burnable absorber coated on the outer surface of the fuel rods

Energy sources. Part A, Recovery, utilization, and environmental effects, 2022-09, Vol.44 (3), p.7650-7664

2022

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Neutronic feasibility study of ( Th - 233 U)-Zr H 1.65 fuel in a modelled TRIGA research reactor

Journal of King Saud University. Science, 2022-02, Vol.34 (2), p.101769, Article 101769

2022

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Investigation of the influence of various reflector elements material types on the core nuclear parameters of the 2 MW Triga Mark-II research reactor using the Monte Carlo code

Turkish journal of physics, 2018, Vol.42, p.41-46

2018

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Processing and benchmarking of evaluated nuclear data file/b-viii.0β4 cross-section library by analysis of a series of critical experimental benchmark using the monte carlo code MCNP(X) and NJOY2016

Nuclear engineering and technology, 2017, Vol.49 (8), p.1610-1616

2017

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Calculation of kinetic parameters of the Moroccan TRIGA mark-II reactor using the Monte Carlo code MCNP

Advances in Applied Physics, 2015, Vol.3, p.1-8

2015

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Benchmark results for the “BWR-PB” fuel assembly based on pebble-bed coated particles with uranium dioxide and gadolinia poison

Nuclear engineering and design, 2009-06, Vol.239 (6), p.1148-1154

2009

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Comparative study between Acuros XB algorithm and Anisotropic Analytical Algorithm in the case of heterogeneity for the treatment of lung cancer

Polish journal of medical physics and engineering, 2018-09, Vol.24 (3), p.115-119

2018

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An inter-comparison between ENDF/B-VIII.0-NECP-Atlas and ENDF/B-VIII.0-NJOY results for criticality safety benchmarks and benchmarks on the reactivity temperature coefficient

Neutron beam characterization for the Moroccan TRIGA Mark II reactor

Processing and benchmarking of evaluated nuclear data file/b-viii.0β4 cross-section library by analysis of a series of critical experimental benchmark using the monte carlo code MCNP(X) and NJOY2016

Neutronic feasibility study of (Th-233U)-ZrH1.65 fuel in a modelled TRIGA research reactor

Neutronic investigation of prospective dual-cooled micro-heterogeneous duplex fuel for small modular long-life reactors: Assembly level design and analysis

Processing of JEFF-3.3 and ENDF/B-VIII.0 and testing with critical benchmark experiments and TRIGA Mark II research reactor using MCNPX

Revolutionizing LWR SMR reactors: exploring the potential of (Th-233U-235U)O2 fuel through a parametric study

The use of burnable absorbers integrated into TRISO/QUADRISO particles as a reactivity control method in a pebble-bed HTR reactor fuelled with (Th,233U)O2

Parametric neutronic analysis of different cladding options for ThO2 pellet of advanced dual-cooled annular PWR assembly

Revolutionizing LWR SMR reactors: exploring the potential of (Th- 233 U- 235 U)O 2 fuel through a parametric study

Uranium and other heavy metal sorption from Moroccan phosphoric acid with argan nutshell sawdust

A comparative analysis of the neutronic performance of thorium mixed with uranium or plutonium in a high‐temperature pebble‐bed reactor

Neutronic and burnup characteristics of potential dual‐cooled annular (Th‐233U‐235U)O2 fuel for the advanced pressurized water reactors: An assembly‐level analysis

Neutronic investigation of the thorium-based mixed-oxide as an alternative fuel in the TRIGA Mark-II research reactor – Part I: A beginning of life calculations

Neutronic and burnup characteristics of potential dual‐cooled annular ( Th‐ 233 U‐ 235 U ) O 2 fuel for the advanced pressurized water reactors: An assembly‐level analysis

Modeling and simulating the induced effect on the steel collimator plug used in the PGAA facility of the Moroccan TRIGA Mark-II reactor under different neutron irradiation levels

New open-source software for gamma-ray spectra analysis

An inter-comparison between ENDF/B-VIII.0-NECP-Atlas and ENDF/B-VIII.0-NJOY results for criticality safety benchmarks and benchmarks on the reactivity temperature coefficient

Neutronic investigation of a VVER-1200 (Th-233U)O2 fuel assembly with protactinium oxide as a burnable absorber coated on the outer surface of the fuel rods

Neutronic feasibility study of ( Th - 233 U)-Zr H 1.65 fuel in a modelled TRIGA research reactor

Investigation of the influence of various reflector elements material types on the core nuclear parameters of the 2 MW Triga Mark-II research reactor using the Monte Carlo code

Processing and benchmarking of evaluated nuclear data file/b-viii.0β4 cross-section library by analysis of a series of critical experimental benchmark using the monte carlo code MCNP(X) and NJOY2016

Calculation of kinetic parameters of the Moroccan TRIGA mark-II reactor using the Monte Carlo code MCNP

Benchmark results for the “BWR-PB” fuel assembly based on pebble-bed coated particles with uranium dioxide and gadolinia poison

Comparative study between Acuros XB algorithm and Anisotropic Analytical Algorithm in the case of heterogeneity for the treatment of lung cancer

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