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Construction of the hourly load curves and detecting the annual peak load of future Syrian electric power demand using bottom-up approach

International journal of electrical power & energy systems, 2009, Vol.31 (1), p.1-12

Hainoun, A.

2009

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Assessment of technology-based options for climate neutrality in Austrian manufacturing industry

Heliyon, 2024-02, Vol.10 (3), p.e25382-e25382, Article e25382

2024

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Estimating the health damage costs of syrian electricity generation system using impact pathway approach

Energy (Oxford), 2010-02, Vol.35 (2), p.628-638

2010

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Formulating an optimal long-term energy supply strategy for Syria using MESSAGE model

Energy policy, 2010-04, Vol.38 (4), p.1701-1714

2010

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International benchmark study of advanced thermal hydraulic safety analysis codes against measurements on IEA-R1 research reactor

Nuclear engineering and design, 2014-12, Vol.280, p.233-250

2014

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Future development of Syrian power sector in view of GHG mitigation options

Renewable & sustainable energy reviews, 2014-10, Vol.38, p.1045-1055

2014

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Measurement of Velocity and Temperature Profiles in the 1/40 Scaled-Down CANDU-6 Moderator Tank

Science and Technology of Nuclear Installations, 2015-01, Vol.2015 (2015), p.270-278

2015

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Modelling of the Radiological Contamination of the RBMK-1500 Reactor Water Purification and Cooling System

Science and Technology of Nuclear Installations, 2014-01, Vol.2014 (2014), p.259-266, Article 1

2014

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Simulation of subcooled flow instability for high flux research reactors with ATHLET

Kerntechnik (1987), 2022-03, Vol.66 (4), p.214-216

2022

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Thermal hydraulic analysis of Syrian MNSR research reactor using RELAP5/Mod3.2 code

Annals of nuclear energy, 2010-04, Vol.37 (4), p.572-581

2010

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Safety analysis of the IAEA reference research reactor during loss of flow accident using the code MERSAT

Nuclear engineering and design, 2010-05, Vol.240 (5), p.1132-1138

2010

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Conceptual design modifications of the cooling system of MNSR reactor to increase its maximum continuous operation time

Nuclear engineering and design, 2007-12, Vol.237 (23), p.2275-2281

2007

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Analysis of the Syrian long-term energy and electricity demand projection using the end-use methodology

Energy policy, 2006-09, Vol.34 (14), p.1958-1970

2006

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Full-scale modelling of the MNSR reactor to simulate normal operation, transients and reactivity insertion accidents under natural circulation conditions using the thermal hydraulic code ATHLET

Nuclear engineering and design, 2005-01, Vol.235 (1), p.33-52

2005

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Determination of major kinetic parameters of the Syrian MNSR for different fuel loading using Monte Carlo technique

Annals of nuclear energy, 2009-11, Vol.36 (11), p.1663-1667

2009

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Simulation of LOFA and RIA for the IEA-R1 research reactor using the code MERSAT

Annals of nuclear energy, 2008-11, Vol.35 (11), p.2093-2104

2008

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Safety analysis of the reference research reactor MTR during reactivity insertion accident using the code MERSAT

Annals of nuclear energy, 2010-06, Vol.37 (6), p.853-860

2010

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Analysis of MNSR core composition changes using the codes WIMSD-4 and CITATION

Applied radiation and isotopes, 2008-10, Vol.66 (10), p.1492-1500

2008

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Regional Energy Demand Analysis Portal (REDAP) Digitalisation: enabling better government decision-making in the building & transport sectors

IOP conference series. Earth and environmental science, 2020-11, Vol.588 (3), p.32008

2020

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Decarbonization scenarios for the industrial energy system in Austria

Elektrotechnik und Informationstechnik, 2021-08, Vol.138 (4-5), p.258

2021

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Simulation of subcooled flow instability for high flux research reactors using the extended code ATHLET

Nuclear engineering and design, 2001-07, Vol.207 (2), p.163-180

2001

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Dynamic analysis of the closed-loop transfer function in the miniature neutron source reactor (MNSR)

Nuclear engineering and design, 2004-07, Vol.232 (1), p.19-28

2004

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Determination of neutron generation time in miniature neutron source reactor by measurement of neutronics transfer function

Nuclear engineering and design, 2000-02, Vol.195 (3), p.299-305

2000

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Comparative safety assessment of HEU and LEU core of MNSR under large reactivity insertion accidents

Annals of nuclear energy, 2014-01, Vol.63, p.624-632

2014

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A comparative assessment of independent thermal-hydraulic models for research reactors: The RSG-GAS case

Nuclear engineering and design, 2014-03, Vol.268, p.77-86

2014

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Construction of the hourly load curves and detecting the annual peak load of future Syrian electric power demand using bottom-up approach

Assessment of technology-based options for climate neutrality in Austrian manufacturing industry

Estimating the health damage costs of syrian electricity generation system using impact pathway approach

Formulating an optimal long-term energy supply strategy for Syria using MESSAGE model

International benchmark study of advanced thermal hydraulic safety analysis codes against measurements on IEA-R1 research reactor

Future development of Syrian power sector in view of GHG mitigation options

Measurement of Velocity and Temperature Profiles in the 1/40 Scaled-Down CANDU-6 Moderator Tank

Modelling of the Radiological Contamination of the RBMK-1500 Reactor Water Purification and Cooling System

Simulation of subcooled flow instability for high flux research reactors with ATHLET

Thermal hydraulic analysis of Syrian MNSR research reactor using RELAP5/Mod3.2 code

Safety analysis of the IAEA reference research reactor during loss of flow accident using the code MERSAT

Conceptual design modifications of the cooling system of MNSR reactor to increase its maximum continuous operation time

Analysis of the Syrian long-term energy and electricity demand projection using the end-use methodology

Full-scale modelling of the MNSR reactor to simulate normal operation, transients and reactivity insertion accidents under natural circulation conditions using the thermal hydraulic code ATHLET

Determination of major kinetic parameters of the Syrian MNSR for different fuel loading using Monte Carlo technique

Simulation of LOFA and RIA for the IEA-R1 research reactor using the code MERSAT

Safety analysis of the reference research reactor MTR during reactivity insertion accident using the code MERSAT

Analysis of MNSR core composition changes using the codes WIMSD-4 and CITATION

Regional Energy Demand Analysis Portal (REDAP) Digitalisation: enabling better government decision-making in the building & transport sectors

Decarbonization scenarios for the industrial energy system in Austria

Simulation of subcooled flow instability for high flux research reactors using the extended code ATHLET

Dynamic analysis of the closed-loop transfer function in the miniature neutron source reactor (MNSR)

Determination of neutron generation time in miniature neutron source reactor by measurement of neutronics transfer function

Comparative safety assessment of HEU and LEU core of MNSR under large reactivity insertion accidents

A comparative assessment of independent thermal-hydraulic models for research reactors: The RSG-GAS case

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