Search Results - "Ehsan Zarifi"

Thermal-hydraulic modeling of CAREM-25 advanced small modular reactor using the porous media approach and COBRA-EN modified code by Ganjaroodi, Saeed Zare, Fani, Maryam, Zarifi, Ehsan, Bentridi, Salaheddine

“…Small Modular Reactors (SMRs) are compact nuclear reactors designed to generate electric power up to 300 MWe. They could be assembled in factory, and then…”
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Loss of offsite power (LOOP) accident analysis by integration of deterministic and probabilistic approaches in Bushehr-1 VVER-1000/V446 nuclear power plant by Esfandiari, Mohsen, Jahanfarnia, Gholamreza, Sepanloo, Kamran, Zarifi, Ehsan

“…The results of an accident analysis for the loss of offsite power (LOOP) scenario in a reference Bushehr-1 VVER-1000/V446 nuclear power plant (NPP) are…”
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Thermal-hydraulic modeling of CAREM-25 advanced small modular reactor using the porous media approach and COBRA-EN modified code by Saeed Zare Ganjaroodi, Maryam Fani, Ehsan Zarifi, Salaheddine Bentridi

“…Small Modular Reactors (SMRs) are compact nuclear reactors designed to generate electric power up to 300 MWe. They could be assembled in factory, and then…”
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Loss of offsite power accident analysis in a VVER-1000/V446 nuclear power plant by Esfandiari, Mohsen, Jahanfarnia, Gholamreza, Sepanloo, Kamran, Zarifi, Ehsan

“…The aim of this study is to present a thermo-hydraulic analysis of the loss of offsite power accident in VVER-1000/V446 nuclear power plant using the RELAP5…”
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Neutronic analysis of new generation TVS-2M fuel assemblies in VVER-1000 reactor type by Ganjaroodi, Saeed Zare, Zarifi, Ehsan, Khameh, Hossein

“…The Russian fuel assembly TVS-2M is a newly proposed fuel configuration that contains gadolinium-oxide at different concentrations mixed with enriched UO2 at…”
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Neutronic investigation of ALFRED lead-Cooled fast reactor core using monte carlo modeling by Ganjaroodi, Saeed Zare, Zarifi, Ehsan

“…A Lead-Cooled Fast Reactor (LFR) is one of the six advanced fourth-generation reactors that many countries have been interested in designing, constructing, or…”
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Thermal-hydraulic analysis of Al2O3 nanofluid as a coolant in Canadian supercritical water reactor by porous media approach by Salehi, Danial, Jahanfarnia, Gholamreza, Zarifi, Ehsan

“…In this study, thermal-hydraulic analysis of Canadian Supercritical Water Reactor (Canadian SCWR) with nanofluid coolant has been done by porous media…”
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Retraction notice to “Subchannel Analysis of TiO2 Nanofluid as the Coolant in VVER-1000 Reactor” Progress in Nuclear Energy 73, (2014), 140-152 by Zarifi, Ehsan, Jahanfarnia, Gholamreza

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Fire simulation in the main control room of Bushehr nuclear power plant using CFAST software by Mojab, Sahar, Zarifi, Ehsan, Ganjaroodi, Saeed Zare, Jahanfarnia, Gholamreza

“…Fire protection is one of the most important issues to ensure safety and reduce risks of nuclear power plants. The main control room (MCR) is one of the parts…”
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Analysis of variation of neutronic and kinetic parameters of a Heavy Water Zero Power Reactor caused by changes in the fuel lattice pitch using MCNPX code by Zarifi, Ehsan, Sepanloo, Kamran, Nazari, Mohammad Nami, Ganjaroodi, Saeed Zare

“…The Heavy Water Zero Power Reactor (HWZPR) is a 100‑W research reactor that uses natural uranium metallic fuel and heavy water as moderator. The HWZPR is…”
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Subchannel analysis of nanofluids application to VVER-1000 reactor by Zarifi, Ehsan, Jahanfarnia, Gholamreza, Veysi, Farzad

“…► We performed the subchannel analysis of nanofluids as a coolant in VVER-1000 reactor. ► Water-based nanofluids with various volume fractions of Al2O3…”
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Thermal–hydraulic modeling of nanofluids as the coolant in VVER-1000 reactor core by the porous media approach by Zarifi, Ehsan, Jahanfarnia, Gholamreza, Veysi, Farzad

“…► The present article is a thermal–hydraulic analysis of nanofluids as the coolant in reactor core. ► The nanofluids thermal conductivity enhancement suggests…”
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Comparison of semi-heavy water and H2O as coolant for a conceptual research reactor from the view point of neutronic parameters by Rahimi, Ghasem, Hadad, Kamal, Nematollahi, Mohammadreza, Zarifi, Ehsan, Sahin, Sumer

“…Although semi-heavy water for nuclear reactors has not been industrialized, however due to its interesting characteristics, many research studies have been…”
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RETRACTED: Subchannel analysis of TiO2 nanofluid as the coolant in VVER-1000 reactor by Zarifi, Ehsan, Jahanfarnia, Gholamreza

“…This article has been retracted: please see Elsevier Policy on Article Withdrawal (http://www.elsevier.com/locate/withdrawalpolicy). This article has been…”
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Neutronic simulation of water-based nanofluids as a coolant in VVER-1000 reactor by Zarifi, Ehsan, Jahanfarnia, Gholamreza, Veysi, Farzad

“…The main goal of this study is to perform the neutronic simulation of nanofluids application to reactor core. The variation of the Bushehr VVER-1000 reactor…”
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Neutronic analysis of nanofluid as a coolant in HPLWR fuel assembly by Ehsan zarifi, Kamran Sepanloo, Naeimodin Mataji Kojouri

“…The main objective of this study is to predict the neutronic behavior of nanofluids as a coolant in the fuel assembly of the HPLWR. The high-performance light…”
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