Accueil › Annuaire des chercheurs › Hamid Boukhal
Hamid Boukhal
Affiliation : Abdelmalek Essaâdi University
- 64Publications (affiliation marocaine)
- 88Publications au total
- 512Citations
- 12Indice h
Profil de recherche
Hamid Boukhal compte 64 publications référencées (1995–2026). Ses travaux paraissent principalement dans « Applied Radiation and Isotopes », « Annals of Nuclear Energy » et « Progress in Nuclear Energy ». Son article le plus cité, « Seasonal variability in 7Be depositional fluxes at Granada, Spain » (2005), a été cité 33 fois. 8 de ces publications datent des trois dernières années d’activité. Ses travaux sont cosignés avec au moins 12 chercheurs, notamment dans des établissements de Yémen, Espagne.
C’est vous ? Faites connaître vos travaux
Créez gratuitement votre profil DzCademia et ajoutez vos articles : ils apparaîtront plus facilement sur Google et dans les assistants d’IA comme ChatGPT. Plus de personnes pourront vous lire et vous citer.
Créer mon profil gratuit Ajouter mes publicationsDomaines de recherche
- Nuclear reactor physics and engineering
- Advanced Radiotherapy Techniques
- Nuclear and radioactivity studies
- Radiation Dose and Imaging
- Nuclear Engineering Thermal-Hydraulics
Publications (64)
- Evaluation of ENDF/B-VIII.0 nuclear data for criticality calculations using machine learning and the SHAP interpretability method
- Development and dosimetric comparison of a voxel-based phantom of Limnonectes macrocephalus for internal radiation evaluation
- Doppler effect evaluation of the TRU-based Moroccan TRIGA Mark II reactor: Applying novel methodologies
- Development and validation of transient neutronic–thermal–hydraulic coupling in OpenNode: A comprehensive benchmark study for 3D LWR core dynamics
- Investigation of photon interaction parameters in Human Body Tissues using GAMOS, FLUKA, and XCOM Studies
- A comparative analysis of the NaI detector response function using GAMOS and FLUKA Monte Carlo simulations
- Development and validation of a comprehensive S-value database for small animal internal dosimetry in nuclear medicine using the DM_Bra mouse phantom
- A novel approach for dose distribution comparison based on image registration principle
- Comparison of OSL and TL dosimetry systems against IEC and ICRP standards
- Sensitivity and uncertainty analysis of effective multiplication factor of KRITZ-1 benchmark using ENDF/B-VIII.0 and JEFF3-3 nuclear data libraries
- Assessment of dead layers thickness of an HPGe detector after an extended operating period using response surface methodology and Box–Behnken design
- Nuclear data sensitivity and uncertainty analysis using a set of benchmarks containing 233 U comparing ENDF/B-VII.1 and ENDF/B- VIII.0 libraries
- Digital graphical user interface as a facilitator for the calibration of radiation monitoring instruments according to ISO 4037:2019 at the national secondary standard dosimetry laboratory of morocco
- GUI development for SSDL to calibrate photon measuring equipment
- Dose metrology: TLD/OSL dose accuracy and energy response performance
- Specific absorbed fractions of electrons and photons for Digimouse voxelized phantom using GATE/GEANT4 Monte-Carlo simulation
- Ionizing radiation metrology at the service of health: quality control of radiopharmaceutical dose calibrators in nuclear medicine unit -accurarcy, reproducibility and linearity tests-
- ISO 4037 2019: ESTABLISHMENT OF X-RAY NARROW-SPECTRUM SERIES USED IN THE NATIONAL SECONDARY STANDARD DOSIMETRY LABORATORY OF MOROCCO
- A Criticality Study of Fast Critical Experimental Benchmarks Using MCNP Code to Qualifying Different Evaluations
- Validation of deterministic code OpenNTP for the analysis of the C5G7-1D benchmark with different configurations
- Sensitivity and uncertainty quantification of neutronic integral data in the TRIGA Mark II research reactor
- Optimization of the n-type HPGe detector parameters using the “design of experiments” technique
- Calculation of X-ray spectra characteristics and kerma to personal dose equivalent Hp(10) conversion coefficients: Experimental approach and Monte Carlo modeling
- GAMOS/GEANT4 simulation and comparison study of X-ray narrow-spectrum series at the national Secondary Standard Dosimetry Laboratory of Morocco
- Neutronic modeling and calculation of the Nuclear Heating Reactor NHR-5 by the deterministic codes DRAGON5 & DONJON5
- Determination of correction factor of self-absorption for lead-210 in environment samples using spike method
- 56Fe, 16O, 1H Elastic and capture cross sections analysis in PCA-REPLICA benchmark
- Monte Carlo and Medical Physics
- Cross sections Data Adjustment For KRITZ-2:13
- Development of a GUI for automating quality control of dose calibrators using Python
- Air-kerma to Hp(0.07), Hp(3), and Hp(10) conversion coefficients for monoenergetic photons
- Analysis of the Recent Nuclear Data through a Fast Benchmarks Highly Enriched Uranium Study Using the Mcnp6.1 Code
- Neutronic study of the 2-MW TRIGA MARK-II research reactor by the deterministic codes DRAGON5 & DONJON5
- Validation study of the reactor physics lattice transport code DRAGON5 & the Monte Carlo code OpenMC by critical experiments of light water reactors
- Sensitivity and uncertainty analysis on keff due to nuclear data in the KRITZ-2:19 – Comparison between JENDL-4.0 and ENDF/B-VII.1
- Adjustment of group cross sections by means of integral data (ENDF/-VII.1)
- 235U capture cross-section adjustment in criticality benchmarks using ENDF/B-VII.1 evaluation
- Analysis of the CREOLE experiment on the reactivity temperature coefficient of the UO2 light water moderated lattices using Monte Carlo transport calculations and ENDF/B-VII.1 nuclear data library
- Conversion coefficients calculation of mono-energetic photons from air-kerma using Monte Carlo and analytical methods
- Conversion coefficients for photon exposure of the human lens eye: EGSnrc and MCNP6 Monte Carlo simulation
- Deterministic evaluation of safety parameters and neutron flux spectra in the MNSR research reactor using DRAGON-4 code
- Validation of DRAGON4/DONJON4 simulation methodology for a typical MNSR by calculating reactivity feedback coefficient and neutron flux
- 235U elastic cross-section adjustment in criticality benchmarks – Comparison between JENDL-4.0 and ENDF/-VII.1
- A temperature effect analysis of the KRITZ-1 benchmark based on keff decomposition and using the JENDL-4.0 and ENDF/B-VII.1 libraries
- Monte Carlo simulation of Varian Linac for 6 MV photon beam with BEAMnrc code
- Sensitivity and Uncertainty Analysis on the Keff Produced by the 1H, 16O, 239Pu and 240Pu Cross Sections Uncertainties
- Evaluation of variance reduction techniques in BEAMnrc Monte Carlo simulation to improve the computing efficiency
- Evaluation of the dosimetric characteristics of 6 MV flattened and unflattened photon beam
- Neutronic and thermal–hydraulic analysis of new irradiation channels inside the Moroccan TRIGA Mark II research reactor core
- 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
- ERSN-OpenMC, a Java-based GUI for OpenMC Monte Carlo code
- Positron-based attenuation correction for Positron Emission Tomography data using MCNP6 code
- Transient behavior during reactivity insertion in the Moroccan TRIGA Mark II reactor using the PARET/ANL code
- Assessment of the Radiological Consequences of a Radioactive Release under Wet Weather Conditions in a Research Reactor Accident Scenario
- Computing Efficiency Improvement in Monte Carlo Simulation of a 12 MV Photon Beam Medical LINAC
- Validation of Monte-Carlo Geant4 code for Saturne 43 LINAC
- Sensitivity and Uncertainty Analysis of the Keff Due to ENDF/B-VII.0 Cross Sections Uncertainties of the Major Isotopes in Nuclear Reactors
- CREOLE experiment study on the reactivity temperature coefficient with sensitivity and uncertainty analysis using the MCNP5 code and different neutron cross section evaluations
- Steady-state thermal-hydraulic analysis of the Moroccan TRIGA MARK II reactor by using PARET/ANL and COOLOD-N2 codes
- Monte Carlo calculation for the development of a BNCT neutron source (1 eV–10 KeV) using MCNP code
- Monte Carlo calculation for the development of a BNCT neutron source (1eV - 10 KeV) using MCNP code
- Seasonal variability in 7Be depositional fluxes at Granada, Spain
- Atmospheric concentrations of 7Be and 210Pb in Granada, Spain
- Radon variation in soil related to the two earthquakes Md 5.2 and 5.3 occurred in Rachidia province (Morocco)
Revues de publication
- Applied Radiation and Isotopes × 9
- Annals of Nuclear Energy × 6
- Progress in Nuclear Energy × 5
- Journal of Radiation Research and Applied Sciences × 5
- Radiation Physics and Chemistry × 4
- Nuclear Engineering and Design × 4
Publications par année
- 20262
- 20252
- 20244
- 20236
- 20226
- 202110
- 20202
- 20196
- 20186
- 20172
Collaborations
Établissements partenaires : Université Ibn-Tofail · National Centre for Nuclear Energy, Science and Technology · Mohammed V University · Université Sultan Moulay Slimane · Ministère de la Santé
Pays des co-auteurs : Yémen · Espagne
Co-auteurs
- El Mahjoub Chakir
- T. El Bardouni
- Omaima Essaad Belhaj
- Sanae El Ouahdani
- Houda El Yaakoubi
- Mustapha Makhloul
- Y. Boulaich
- Assia Arectout
- Khaoula Laazouzi
- Maryam Hadouachi
- M. Kaddour
- Maged Mohammed
Données bibliographiques issues d’OpenAlex (base ouverte).
Pourquoi choisir Dzcademia ?
Pour donner à vos travaux plus de chances d’être découverts et recommandés par les IA. Profils, articles et communications : donnez à votre recherche une présence publique structurée. Les métadonnées intégrées aident les moteurs de recherche et les assistants IA à identifier vos travaux et à comprendre leurs références.
Commenter avec Google
Connecte-toi avec Google pour commenter directement sur cette page.