الرئيسية › دليل الباحثين › Hamid Amsil
Hamid Amsil
الانتماء : National Centre for Nuclear Energy, Science and Technology
- 92منشورات (انتماء مغربي)
- 111مجموع المنشورات
- 691الاستشهادات
- 15مؤشر h
الملف البحثي
لدى Hamid Amsil 92 منشور(ات) مفهرسة (2009–2026). تُنشر أعماله أساسًا في «Journal of Radioanalytical and Nuclear Chemistry»، «International Journal of Nuclear Energy Science and Technology» و«Nuclear Analysis». أكثر مقالاته استشهادًا هو «Radiological characterization of phosphate rocks, phosphogypsum, phosphoric acid and phosphate fertilizers in Morocco: An assessment of the » (2020)، وقد استُشهد به 50 مرة. 47 من هذه المنشورات تعود إلى آخر ثلاث سنوات من النشاط. شارك في تأليف أعماله 12 باحثًا على الأقل، منهم باحثون من مؤسسات في تونس، الكونغو، جنوب أفريقيا.
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إنشاء ملفي المجاني إضافة منشوراتيمجالات البحث
- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Radiation Detection and Scintillator Technologies
- Heavy metals in environment
- Nuclear Materials and Properties
المنشورات (92)
- Monte Carlo analysis of prompt gamma activation analysis (PGAA): Influence of collimator and filter parameters
- Elemental composition and health risk assessment of heavy metals in medicinal plant Origanum elongatum from Northern Morocco
- Integrated analysis of thermal stability and radioactivity of a PGAA beam at the TRIGA reactor
- A comprehensive assessment of neutronic and thermal–hydraulic behavior of some advanced accident-tolerant fuels in solid and dual-cooled annular PWR assemblies
- Monte Carlo Simulation of Neutron and Gamma Ray Behavior in the PGAA System of the TRIGA Reactor Using the PHITS Code
- Coupled thermo-mechanical modeling of prompt gamma neutron activation analysis (PGAA) systems for performance optimization
- Neutron induced activation and longterm radioactivity assessment of a PGAA system at the TRIGA mark II reactor by Monte Carlo simulation
- Integration and validation of a statistical analysis model for assessing gamma detector reliability in GSA v4 software
- High-resolution trace element profiling of culinary spices using ICP-MS: a comparative study on nutritional and toxicological markers for food safety surveillance
- Elemental profiling of Cannabis sativa L. seeds from Northern Morocco using neutron activation analysis technique at CNESTEN-Morocco
- Radiological performance of cemented FMA-VC radioactive waste packages for transport: A PHITS Monte Carlo study
- High-resolution Monte Carlo investigation of the spatial distribution of neutron and photon absorbed doses in a polyethylene shuttle for soil sample irradiation
- A DPSIR Framework to Analyze the Purpose of Using Nuclear Techniques for Marine Environment Protection
- Neutronic and thermal-hydraulic performance analysis of a novel thorium-based fuel in dual-cooled annular assemblies for SMR applications
- Natural radioactivity and radiological risk in soils of the Oued Beht watershed (Morocco): baseline assessment in a semi-arid catchment hosting a fluorite mine
- Multi-criteria decision analysis of neutron activation platforms for sustainable nuclear analytical infrastructure
- Comparative neutronic analysis and safety-related neutronic considerations of thorium-based fuels under different loading patterns in a Westinghouse-SMR-like core
- Experimental Characterization and Statistical Analysis of Two Geiger-Müller Detectors After Several Years of Use
- Natural gamma radioactivity, ingestion dose, and excess lifetime cancer risk in medicinal plants from northern Morocco
- Modeling radiation aging in polymers under irradiation: application to polyethylene
- Precise efficiency calibration of a p-type HPGe detector: dead layer optimization and near-field TCS analysis via PHITS simulation
- Integrated Monte Carlo and Multiphysics Modeling for the Design, Optimization, and Aging Assessment of Reactor-Based PGAA Facilities: A Comprehensive Review
- Neutron activation analysis at the Moroccan TRIGA MARK II reactor: state of the art, methodological advances, applications and future perspectives
- A virtual HPGe detector framework combining Geant4 and machine learning for detector-response prediction and self-absorption correction
- Numerical Investigation of Heat Generation and Structural Performance of Materials Under Neutron Irradiation
- An automatic efficiency calibration method with high precision for HPGe detectors
- Second version of the open-source software GSA for gamma-ray spectrum analysis
- Software developed to simulate and optimize Geiger-Müller detectors and study gamma ray attenuation
- Innovative thorium-based fuel assemblies for LW-SMR: In-depth assembly-level neutronic analysis and safety considerations in solid and annular configurations
- Design and performance evaluation of a prompt-gamma activation analysis (PGAA) system using Monte Carlo simulation with PHITS
- Multi-method approaches for gamma spectrometry software: calibration, peak analysis, and corrections
- Optimization and validation of HPGE detector efficiency calibration using Monte Carlo, LabSOCS simulations, and experimental measurements
- Monte Carlo simulation and optimization of the PGAA system: impact of emission angle, source–collimator distance, and thermal dissipation
- Activation and mechanical aging of the collimator and shutter of the PGAA system in the TRIGA MARK II reactor: a Monte Carlo and finite element approach
- Chemical composition analysis of argan kernel, leaves and shell from the Oujda region using neutron activation analysis technique at CNESTEN-Morocco
- Thermal-hydraulic investigation of novel thorium-uranium fuel mixtures in advanced SMR assembly configurations
- Comprehensive analysis of heavy metals content in organic and conventional vegetables and their health risk assessment
- Elemental characterization of argan kernels from different regions of Souss Massa Draa (Morocco) using instrumental neutron activation analysis (INAA)
- Innovative burnable absorbers: Assessing PaO2 and NpO2 coatings for improved safety in (Th-233U-235U)O2 fuel assemblies
- Temperature distribution in the PGAA system: Collimator, shutter, and filter in TRIGA Mark II reactor
- Evaluation of Potassium-40 and Uranium-238 activities and radiological risk in Missour, Morocco soils using gamma spectrometry
- Major and trace elements determination in organic and conventional Moroccan vegetables using the k0-standardisation method of neutron activation analysis
- Ecological risk assessment of soil samples from Sudanese gold-mining regions using neutron activation analysis
- In-depth Study of Radioactive Isotope Profiles 234U, 235U, and 238U in Earth Samples from the Missour Region, Morocco: A Detailed Exploration of Nuclear Activity
- Neutron irradiation-induced modifications in polyethylene properties within nuclear environments: analysis of shuttles irradiated in the TRIGA Mark II reactor
- Geochemical Analysis of Coastal Sediments near Larache and Moulay Bousselham, Morocco
- Leveraging nuclear gamma technology for the sustainable preservation and quality improvement of spices
- Utilizing the k0-IAEA program to determine rare earth elements in soil samples from gold-mining areas in Sudan
- Utilization of k0-standardisation method of neutron activation analysis for determining the major and trace elements of medicinal plants from the Senhaja Srair region of Morocco
- Major and trace elements Content in Cannabis Sativa–L cultivated in North of Morocco and Heavy metals health risk assessment
- Characterisation of neutron flux spectra with PGNAA shutter: a computational approach
- Kayzero-standardization method of neutron activation analysis study for major and minor elements determined in soils and phosphate rocks of the prospective phosphate mining area in the Hinda district, Republic of Congo
- The Moroccan PGAA System: Design, Installation, and Challenges.
- Geochemical characterization of rare earth elements in sediment profiles from the Oualida lagoon (Morocco)
- Combination of k0-IAEA and KayWin for the characterization of neutron flux parameters at Triga Mark II research reactor, Morocco
- Investigating Geochemical Patterns of Major and Trace El-ements in Granitic Rocks of the Oulmes Region, Central Morocco: Instrumental Neutron Activation Analysis (INAA)
- Ecological and health risk assessments of rare earth elements in soil from gold mining areas in Sudan
- Neutron and Gamma Flux Distributions of an Americium–Beryllium Facility: Modelling and Simulation
- Spallation reaction study to improve cross-section measurements of fission products in nuclear waste using Cs-137 on proton or deuteron ranging from 0.1 to 2.4 GeV
- Quality Assurance in Neutron Activation Analysis: Simulation and a Continuous Improvement Approach
- Spallation reaction study to improve cross-section measurements of fission products in nuclear waste using Cs-137 on proton or deuteron ranging from 0.1 to 2.4 GeV
- Enhancing analytical techniques and measurement procedures in the TRIGA Mark II neutron activation analysis laboratory: leveraging simulation and continuous evaluation strategies
- New open-source software for gamma-ray spectra analysis
- 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
- Potential ecological risk assessment of rare earth elements in sediments cores from the Oualidia lagoon, Morocco
- 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
- Comparison of relative and k0 neutron activation analysis methods at MA-R1 TRIGA MARK II Research Reactor of CNESTEN (Morocco)
- 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
- A comparative analysis of the neutronic performance of thorium mixed with uranium or plutonium in a high‐temperature pebble‐bed reactor
- Neutron guide optimization for the Moroccan PGAA system
- 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
- 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
- Performance of k0 standardization method in neutron activation analysis using Kayzero for Windows software at the National Center for Energy, Sciences and Nuclear Techniques (CNESTEN-Morocco)
- Neutron beam characterization for the Moroccan TRIGA Mark II reactor
- Improvement of Neutron Safety Performance of Devices Used in the Prompt Gamma Activation Analysis Technique (PGAA) in Morocco: Modeling and Simulation
- Neutronic feasibility study of ( Th-233U)-ZrH1.65 fuel in a modelled TRIGA research reactor
- Radiological characterization of phosphate rocks, phosphogypsum, phosphoric acid and phosphate fertilizers in Morocco: An assessment of the radiological hazard impact on the environment
- Tracking natural and human impact on sediment dynamics using radiometric approach in Oualidia lagoon (Morocco)
- Conceptual implementation stages for Moroccan PGAA/NI instruments: STAGE I & II
- Determining PGAA collimator plug design using Monte Carlo simulation
- Collimator and sapphire filter using for the prompt gamma neutron activation analysis facility: modelling and simulation
- 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
- Simulation of a collimator and sapphire filter for PGAA facility of the Moroccan TRIGA MARK II research reactor
- Water Quality of El Hachef River (Region of Tangier-Tetouan-AL Houceima, North West Morocco)
- Geochemical, radiometric, and environmental approaches for the assessment of the intensity and chronology of metal contamination in the sediment cores from Oualidia lagoon (Morocco)
- Study of heavy metal assessment in the Gharb plain along Sebou river (Morocco) using k0-NAA method at the Moroccan Triga Mark II research reactor
- Neutron flux characterization of the Moroccan Triga Mark II research reactor and validation of the k 0 standardization method of NAA using k 0-IAEA program
- Determination of elemental impurities in phosphoric acid by INAA employing a novel method of phosphate precipitation
- Burnup characteristic of CERMET and TRISO fuel particles used in Boiling Water Reactor with Pebble-Bed Coated Particles
- Neutronic calculations of AFPR-100 reactor based on Spherical Cermet Fuel particles
- A neutronic assessment of the new Spherical Cermets Fuel concept for the BWR-PB reactor
- Benchmark results for the “BWR-PB” fuel assembly based on pebble-bed coated particles with uranium dioxide and gadolinia poison
مجلات النشر
- Journal of Radioanalytical and Nuclear Chemistry × 15
- International Journal of Nuclear Energy Science and Technology × 8
- Nuclear Analysis × 6
- Annals of Nuclear Energy × 5
- Applied Radiation and Isotopes × 5
- Nuclear Engineering and Design × 4
المنشورات حسب السنة
- 202625
- 202513
- 20249
- 202315
- 20225
- 20219
- 20205
- 20193
- 20182
- 20143
التعاون العلمي
المؤسسات الشريكة : Université Ibn-Tofail · Mohammed V University · Sidi Mohamed Ben Abdellah University · Université Hassan 1er · Mohamed I University
بلدان المؤلفين المشاركين : تونس · الكونغو · جنوب أفريقيا
المؤلفون المشاركون
- Hamid Bounouira
- Abdessamad Didi
- Iliasse Aarab
- Abdelwahab Badague
- Abdelouahed Chetaine
- Khalid Laraki
- Jamila Yousfi
- El Mahjoub Chakir
- Hamid Marah
- Abdelfettah Benchrif
- Ouadie Kabach
- Khalid Embarch
البيانات البيبليوغرافية مصدرها OpenAlex (قاعدة مفتوحة).
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