الرئيسية › دليل الباحثين › Tewfik Hamidouche

Tewfik Hamidouche

الانتماء : Centre de Recherche Nucléaire d’Alger · University of Sciences and Technology Houari Boumediene

• 14منشورات (انتماء جزائري)
• 35مجموع المنشورات
• 436الاستشهادات
• 11مؤشر h

ORCIDOpenAlex

مجالات البحث

• Nuclear Engineering Thermal-Hydraulics
• Nuclear reactor physics and engineering
• Heat transfer and supercritical fluids
• Nuclear and radioactivity studies
• Nuclear Materials and Properties

المنشورات (14)

• Analysis of loss of coolant accident in MTR pool type research reactor
  2011 · Progress in Nuclear Energy · استُشهد به 20 مرة
• Application of coupled code technique to a safety analysis of a standard MTR research reactor
  2009 · Nuclear Engineering and Design · استُشهد به 30 مرة
• Assessment of RELAP5 point kinetic model against reactivity insertion transient in the IAEA 10 MW MTR research reactor
  2009 · Nuclear Engineering and Design · استُشهد به 19 مرة
• NUMERICAL INVESTIGATION FOR PREDICTING THE ONSET OF FLOW INSTABILITY UNDER RESEARCH REACTOR’S CONDITION
  2009 · International Symposium on Convective Heat and Mass Transfer (CONV)
• Analysis of Rod Ejection Accident in a Research Reactor by the Coupled Technique
  2009 · Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications
• Overview of accident analysis in nuclear research reactors
  2008 · Progress in Nuclear Energy · استُشهد به 36 مرة
• Simplified numerical model for defining Ledinegg flow instability margins in MTR research reactor
  2008 · Progress in Nuclear Energy · استُشهد به 17 مرة
• INVESTIGATION OF EXCURSION INSTABILITY IN FORCED CONVECTION IN A VERTICAL HEATED CHANNEL
  2008 · International Symposium on Advances in Computational Heat Transfer (CHT)
• RELAP5/3.2 assessment against low pressure onset of flow instability in parallel heated channels
  2006 · Annals of Nuclear Energy · استُشهد به 48 مرة
• Assessment of RELAP5 model for the University of Massachusetts Lowell Research Reactor
  2006 · Nuclear Technology and Radiation Protection · استُشهد به 11 مرة
• A model for the analysis of loss of decay heat removal during loss of coolant accident in MTR pool type research reactors
  2006 · Annals of Nuclear Energy · استُشهد به 11 مرة
• Analysis of partial and total flow blockage of a single fuel assembly of an MTR research reactor core
  2005 · Annals of Nuclear Energy · استُشهد به 65 مرة
• Analysis of the IAEA research reactor benchmark problem by the RETRAC-PC code
  2005 · Nuclear Engineering and Design · استُشهد به 32 مرة
• Dynamic calculations of the IAEA safety MTR research reactor Benchmark problem using RELAP5/3.2 code
  2004 · Annals of Nuclear Energy · استُشهد به 91 مرة

مجلات النشر

• Annals of Nuclear Energy × 4
• Progress in Nuclear Energy × 3
• Nuclear Engineering and Design × 3
• International Symposium on Convective Heat and Mass Transfer (CONV) × 1
• Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications × 1
• International Symposium on Advances in Computational Heat Transfer (CHT) × 1

المنشورات حسب السنة

• 20111
• 20094
• 20083
• 20063
• 20052
• 20041

التعاون العلمي

المؤسسات الشريكة : University of Boumerdes

المؤلفون المشاركون

• El‐Khider Si‐Ahmed
• Nouara Rassoul
• Brahim Meftah
• E-K. Si Ahmed
• Ibrahim Rassoul
• Hakim El Hadjen

البيانات البيبليوغرافية مصدرها OpenAlex (قاعدة مفتوحة).