الرئيسية › دليل الباحثين › Hakim Mazrou
Hakim Mazrou
الانتماء : Centre de Recherche Nucléaire d’Alger
- 31منشورات (انتماء جزائري)
- 31مجموع المنشورات
- 341الاستشهادات
- 10مؤشر h
الملف البحثي
لدى Hakim Mazrou 31 منشور(ات) مفهرسة (2004–2026). تُنشر أعماله أساسًا في «SSRN Electronic Journal»، «Annals of Nuclear Energy» و«Progress in Nuclear Energy». أكثر مقالاته استشهادًا هو «Monte Carlo calculations of the HPGe detector efficiency for radioactivity measurement of large volume environmental samples» (2015)، وقد استُشهد به 50 مرة. 11 من هذه المنشورات تعود إلى آخر ثلاث سنوات من النشاط. شارك في تأليف أعماله 12 باحثًا على الأقل.
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إنشاء ملفي المجاني إضافة منشوراتيمجالات البحث
- Nuclear reactor physics and engineering
- Nuclear Physics and Applications
- Radiation Detection and Scintillator Technologies
- Nuclear Engineering Thermal-Hydraulics
- Nuclear and radioactivity studies
المنشورات (31)
- Advancing Neutronic‒Thermal-Hydraulic Coupling for Safety Assessment of MTR-Type Research Reactors: Application to Steady-State and Transient Analysis of OPAL Research Reactor
- Comparative Assessment of RELAP5, PLTEMP/ANL and PARET/ANL Codes for Steady-State Thermal Hydraulic Safety Analysis of the OPAL Research Reactor
- Bridging System-Code and Subchannel Approaches: A Pseudo-2D Thermal-Hydraulic Modeling Strategy Based on RELAP5 Safety analysis of an MTR-Type Research Reactor Core
- Assessing the impact of modeling assumptions on steady-state thermal-hydraulic safety margins in research reactors: The OPAL case
- A Monte Carlo-based two-step neutronic‒thermal-hydraulic coupling framework for steady-state and transient analysis of the OPAL research reactor
- Bridging System-Code and Subchannel Approaches: A Pseudo-2D Thermal-Hydraulic Modeling Strategy for MTR-Type Research Reactor Cores using RELAP5/Mod3.2
- Cross-Verification and validation of steady-state OPAL research reactor neutronic models using OpenMC and MCNP5 Codes: A foundation for advanced coupled simulations
- Performance evaluation and validation of OpenMC code for criticality analysis of an MTR-type research reactor
- Development and validation of a Bayesian unfolding program using OpenBUGS open-source software for Bonner spheres neutron spectrometry
- Software-Based automation of burnup calculations for the NUR research reactor using SCALE/TRITON T6-DEPL sequence
- A Complete Comparative Study of Openmc and Mcnp5 Codes for the Criticality Analysis of Mtr-Type Research Reactors
- Assessment of the safety impact caused by the variations of the critical position of control rods and by the presence of an in-core flux trap on the power peaking factors in an MTR-type research reactor
- Investigation of the Effects of Critical Control Rod Positions and Core Configurations on Hot Channel Locations and Power Peaking Factors in an Mtr-Type Research Reactor
- Monte Carlo study of organ doses and related risk for cancer in Algeria from scattered neutrons in prostate treatment involving 3D-CRT
- Evaluation of a neutron spectrum from Bonner spheres measurements using a Bayesian parameter estimation combined with the traditional unfolding methods
- Monte Carlo modeling of the NUR Nuclear Research Reactor
- Investigation and improvement of the solution neutron spectrum around an 241Am-Be based neutron irradiator using the traditional unfolding procedure
- Convergence assessment of the MCNP5 model for NUR research reactor
- Neutron spectrum measurements at a radial beam port of the NUR research reactor using a Bonner spheres spectrometer
- Monte Carlo calculations of the HPGe detector efficiency for radioactivity measurement of large volume environmental samples
- Monte Carlo estimation of photoneutrons spectra and dose equivalent around an 18MV medical linear accelerator
- Neutron field measurements of the CRNA OB26 irradiator using a bonner sphere spectrometer for radiation protection purposes
- MCNP5 evaluation of a response matrix of a Bonner Sphere Spectrometer with a high efficiency 6LiI (Eu) detector from 0.01 eV to 20 MeV neutrons
- Neutron field characterisation of the OB26 CRNA irradiator in view of its use for calibration purposes
- Monte-Carlo investigation of radiation beam quality of the CRNA neutron irradiator for calibration purposes
- Characterization of an Am–Be PGNAA set-up developed for in situ liquid analysis: Application to domestic waste water and industrial liquid effluents analysis
- Performance improvement of artificial neural networks designed for safety key parameters prediction in nuclear research reactors
- Characterization of the CRNA Bonner sphere spectrometer based on 6LiI scintillator exposed to an 241Am–Be neutron source
- Monte Carlo optimization of sample dimensions of an 241Am–Be source-based PGNAA setup for water rejects analysis
- Development of a supporting tool for optimal fuel management in research reactors using artificial neural networks
- Application of artificial neural network for safety core parameters prediction in LWRRS
مجلات النشر
- SSRN Electronic Journal × 6
- Annals of Nuclear Energy × 4
- Progress in Nuclear Energy × 3
- Nuclear Engineering and Design × 3
- Applied Radiation and Isotopes × 3
- Radiation Measurements × 2
المنشورات حسب السنة
- 20266
- 20251
- 20244
- 20232
- 20211
- 20184
- 20161
- 20151
- 20131
- 20121
التعاون العلمي
المؤسسات الشريكة : University of Sciences and Technology Houari Boumediene · University of Boumerdes · University of Blida 2 · University of Blida
المؤلفون المشاركون
- Djahid Lababsa
- Malika Allab
- Zahir Idiri
- Tassadit Sidahmed
- Hamza Hasnaoui
- Djalal Hamed
- Zohra Lounis-Mokrani
- S. Bedek
- Ourida Mokhtari
- M. Belgaid
- Fethi Bezoubiri
- Abdelkader Aouaichia
البيانات البيبليوغرافية مصدرها OpenAlex (قاعدة مفتوحة).
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