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Employment (1)

Shiraz University: Shiraz, Fars, IR

1999 to present | Associate Professor (Nuclear Engineering)
Employment
Source: Self-asserted source
Mohammad Reza Nematollahi

Works (44)

Using MCNP for success criteria evaluation of reactor trip function in probabilistic modeling of ATWS upon LOOP

Progress in Nuclear Energy
2018 | Journal article
EID:

2-s2.0-85044611840

Contributors: Kamyab, S.; Nematollahi, M.R.; Hadad, K.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Neutronic-thermal hydraulic coupling analysis of the fuel channel of a new generation of the small modular pressurized water reactor including hexagonal and square fuel assemblies using MCNP and CFX

Progress in Nuclear Energy
2017 | Journal article
EID:

2-s2.0-85017107526

Contributors: Erfaninia, A.; Hedayat, A.; Mirvakili, S.M.; Nematollahi, M.R.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Assessment of thermal hydraulics parameters of the VVER-1000 during transient conditions

International Journal of Hydrogen Energy
2016 | Journal article
EID:

2-s2.0-84962705288

Contributors: Bagheri, S.; Faghihi, F.; Nematollahi, M.R.; Behzadinejad, B.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

CFX study of flow accelerated corrosion via mass transfer coefficient calculation in a double elbow

International Journal of Hydrogen Energy
2016 | Journal article
EID:

2-s2.0-84977962652

Contributors: Keshtkar, K.; Nematollahi, M.; Erfaninia, A.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Moderation and shielding optimization for a<sup>252</sup>Cf based prompt gamma neutron activation analyzer system

International Journal of Hydrogen Energy
2016 | Journal article
EID:

2-s2.0-84957706088

Contributors: Hadad, K.; Nematollahi, M.; Sadeghpour, H.; Faghihi, R.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Numerical study of mass transfer coefficient in a T-junction

International Journal of Hydrogen Energy
2016 | Journal article
EID:

2-s2.0-84957053406

Contributors: Erfaninia, A.; Nematollahi, M.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Source substitution and optimization of CBXâ„¢ PGNAA analyzer in Kangan cement plant

Progress in Nuclear Energy
2016 | Journal article
EID:

2-s2.0-84964022171

Contributors: Hadad, K.; Sadeghpour, H.; Nematollahi, M.R.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Dose assessment of radionuclides dispersion from Bushehr nuclear power plant stack under normal operation and accident conditions

International Journal of Hydrogen Energy
2015 | Journal article
EID:

2-s2.0-84936806242

Contributors: Pirouzmand, A.; Dehghani, P.; Hadad, K.; Nematollahi, M.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Experimental and numerical void fraction measurement for modeled two-phase flow inside a vertical pipe

Annals of Nuclear Energy
2015 | Journal article
EID:

2-s2.0-84953876546

Contributors: Adineh, M.; Nematollahi, M.; Erfaninia, A.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Reduction of core damage frequency via new design for emergency core cooling system in a typical PWR

International Journal of Hydrogen Energy
2015 | Journal article
EID:

2-s2.0-84928681912

Contributors: Nematollahi, M.; Erfaninia, A.; Salatini, S.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Void fraction measurement in modeled two-phase flow inside a vertical pipe by using polyethylene phantoms

International Journal of Hydrogen Energy
2015 | Journal article
EID:

2-s2.0-84937831285

Contributors: Faghihi, R.; Nematollahi, M.; Erfaninia, A.; Adineh, M.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Visualization experiment of complex flow field in a sphere-packed pipe by detailed PIV measurement

Fusion Engineering and Design
2014 | Journal article
EID:

2-s2.0-84905904017

Contributors: Ebara, S.; Nematollahi, M.R.; Hashizume, H.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Numerical study of single and two-phase models of water/Al 2O3 nanofluid turbulent forced convection flow in VVER-1000 nuclear reactor

Annals of Nuclear Energy
2013 | Journal article
EID:

2-s2.0-84879035289

Contributors: Hadad, K.; Rahimian, A.; Nematollahi, M.R.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Sensitivity analysis on the effect of software-induced common cause failure probability in the computer-based reactor trip system unavailability

Annals of Nuclear Energy
2013 | Journal article
EID:

2-s2.0-84875181194

Contributors: Kamyab, S.; Nematollahi, M.; Shafiee, G.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Augmented safety heat transport in research reactor IR-40 using nanofluid

ATW - Internationale Zeitschrift fur Kernenergie
2012 | Journal article
EID:

2-s2.0-84869040720

Contributors: Nazififard, M.; Nematollahi, M.; Jafarpour, K.; Suh, K.Y.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Comparison of T-junction flow pattern of water and sodium for different geometries of power plant piping systems

Annals of Nuclear Energy
2012 | Journal article
EID:

2-s2.0-80054109864

Contributors: Nematollahi, M.; Khonsha, B.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Computational analysis for research reactor ir-40 rod bundle

ATW - Internationale Zeitschrift fur Kernenergie
2012 | Journal article
EID:

2-s2.0-84869051850

Contributors: Nazififard, M.; Nematollahi, M.; Jafarpur, K.; Suh, K.Y.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Experimental evaluation of natural circulation pressure drop in a boiling channel

Fusion Science and Technology
2012 | Journal article
EID:

2-s2.0-84857546998

Contributors: Nematollahi, M.; Rezaiean, M.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Failure analysis of low pressure evaporator tubes in a typical Combined Cycle Power Plant

Applied Mechanics and Materials
2012 | Book
EID:

2-s2.0-81255161285

Contributors: Nematollahi, M.; Rezaeian, M.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

FLUENT simulation of nanofluid in subchannel of a typical PWR

Transactions of the American Nuclear Society
2012 | Conference paper
EID:

2-s2.0-84876576334

Contributors: Nazififard, M.; Nematollahi, M.R.; Suh, K.Y.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Numerical simulation of water-based alumina nanofluid in subchannel geometry

Science and Technology of Nuclear Installations
2012 | Journal article
EID:

2-s2.0-84869027018

Contributors: Nazififard, M.; Nematollahi, M.; Jafarpur, K.; Suh, K.Y.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Performance evaluating of the AP1000 passive safety systems for mitigation of small break loss of coolant accident using risk assessment tool-II software

Nuclear Engineering and Design
2012 | Journal article
EID:

2-s2.0-84873364666

Contributors: Kamyab, S.; Nematollahi, M.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Quantitative evaluation of heat transfer in bubble collapse process in subcooled flow boiling

Fusion Science and Technology
2012 | Journal article
EID:

2-s2.0-84857528100

Contributors: Nematollahi, M.; Mazhari, M.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Simulation of a control rod ejection accident in a VVER-1000/V446 using RELAP5/Mod3.2

Annals of Nuclear Energy
2012 | Journal article
EID:

2-s2.0-84860436808

Contributors: Tabadar, Z.; Hadad, K.; Nematollahi, M.R.; Jabbari, M.; Khaleghi, M.; Hashemi-Tilehnoee, M.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Evaluating the core damage frequency of a TRIGA research reactor using risk assessment tool software

Nuclear Engineering and Design
2011 | Journal article
EID:

2-s2.0-79961024359

Contributors: Kamyab, S.; Nematollahi, M.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Numerical analysis of water-based nanofluid coolant for small modular reactor

ASME 2011 Small Modular Reactors Symposium, SMR 2011
2011 | Conference paper
EID:

2-s2.0-84881453204

Contributors: Nazififard, M.; Nematollahi, M.; Suh, K.Y.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Coupling CFAST fire modeling and SAPHIRE probabilistic assessment software for internal fire safety evaluation of a typical TRIGA research reactor

Reliability Engineering and System Safety
2010 | Journal article
EID:

2-s2.0-73649143482

Contributors: Safaei Arshi, S.; Nematollahi, M.; Sepanloo, K.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Evaluating the core damage frequency of a TRIGA research reactor using Risk Assessment Tool software

Proceedings of the International MultiConference of Engineers and Computer Scientists 2010, IMECS 2010
2010 | Conference paper
EID:

2-s2.0-79952409388

Contributors: Nematollahi, M.; Kamyab, Sh.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Evaluating the reliability of AP1000 passive core cooling systems with Risk Assessment Tool

Proceedings of the International MultiConference of Engineers and Computer Scientists 2010, IMECS 2010
2010 | Conference paper
EID:

2-s2.0-79952399158

Contributors: Kamyab, Sh.; Nematollahi, M.; Kamyab, M.; Jafari, A.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Using risk assessment tool to evaluate the fire-induced core damage frequency

WCE 2010 - World Congress on Engineering 2010
2010 | Conference paper
EID:

2-s2.0-79959817847

Contributors: Kamyab, S.; Nematollahi, M.; Famourihoseinzadeh, M.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

A simulation of a steam generator tube rupture in a VVER-1000 plant

Energy Conversion and Management
2008 | Journal article
EID:

2-s2.0-43849087380

Contributors: Nematollahi, M.R.; Zare, A.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Development and application of a Risk Assessment Tool

Reliability Engineering and System Safety
2008 | Journal article
EID:

2-s2.0-40949158409

Contributors: Majdara, A.; Nematollahi, M.R.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Enhancement of heat transfer in a typical pressurized water reactor by different mixing vanes on spacer grids

Energy Conversion and Management
2008 | Journal article
EID:

2-s2.0-44149094558

Contributors: Nematollahi, M.R.; Nazifi, M.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Determination of shielding parameters for different types of concretes by Monte Carlo methods

13th International Conference on Emerging Nuclear Energy Systems 2007, ICENES 2007
2007 | Conference paper
EID:

2-s2.0-79959493713

Contributors: Aminian, A.; Nematollahi, M.R.; Haddad, K.; Mehdizadeh, S.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Enhancement of heat transfer in a typical pressurized water reactor by new mixing vanes on spacer grids

13th International Conference on Emerging Nuclear Energy Systems 2007, ICENES 2007
2007 | Conference paper
EID:

2-s2.0-79959518559

Contributors: Nematollahi, M.R.; Nazifi, M.; Hadad, K.; Faghihi, F.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Typical steam generator tube rupture (SGTR) effect on thermo-hydraulic parameters of VVER-1000 primary loop

13th International Conference on Emerging Nuclear Energy Systems 2007, ICENES 2007
2007 | Conference paper
EID:

2-s2.0-79959511294

Contributors: Zare, A.; Nematollahi, M.R.; Hadad, K.; Mozaffari, M.A.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Comparison of flow-induced vibrations versus subcooled boiling-induced vibrations on a heated rod in axial flow

American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
2006 | Conference paper
EID:

2-s2.0-34547878702

Contributors: Akbari, M.H.; Nematollahi, M.R.; Hashizume, H.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Comparison of flow-induced vibrations versus subcooled boiling-induced vibrations on a heated rod in axial flow

American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
2006 | Conference paper
EID:

2-s2.0-33751309419

Contributors: Akbari, M.H.; Nematollahi, M.R.; Hashizume, H.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Nuclear fuel depletion analysis using matlab software

International Journal of Modern Physics C
2006 | Journal article
EID:

2-s2.0-33745159318

Contributors: Faghihi, F.; Nematollahi, M.R.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Vibration mechanisms of a heated rod due to subcooled boiling flow

American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
2006 | Conference paper
EID:

2-s2.0-34547914097

Contributors: Nematollahi, M.R.; Akbari, M.H.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Vibration mechanisms of a heated rod due to subcooled boiling flow

American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
2006 | Conference paper
EID:

2-s2.0-33751350041

Contributors: Nematollahi, M.R.; Akbari, M.H.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Probabilistic safety assessment of Tehran research reactor

Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04
2004 | Conference paper
EID:

2-s2.0-14844321670

Contributors: Hosseini, S.M.H.; Nematollahi, M.R.; Sepanloo, K.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Thermo-hydraulic simulation of pressurizer in transient cases

Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04
2004 | Conference paper
EID:

2-s2.0-14844309741

Contributors: Ardeshir, A.T.; Nematollahi, M.; Sepanloo, K.; Daneshvari, F.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier

Vibration characteristic of heated rod induced by subcooled flow boiling

Journal of Nuclear Science and Technology
1999 | Journal article
EID:

2-s2.0-0032656195

Contributors: Nematollahi, M.R.; Toda, S.; Hashizume, H.; Yuki, K.
Source: Self-asserted source
Mohammad Reza Nematollahi via Scopus - Elsevier