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Dr. Ali Akbar Salehi is a professor in Nuclear Energy Engineering at Department of Energy Engineering, SHARIF University of Technology in Tehran, IRAN.

Education

  • Ph.D. 1978

    Ph.D. in Nuclear Engineering

    MIT, USA

  • M.S. 1972

    One-year M.S Physics

    American University of Beirut (AUB), Lebanon

  • B.S. 1971

    Physics

    American University of Beirut (AUB) ,Lebanon

Research Interests

Interests

  • Work on Resonance Cross-section Interference Effects
  • Dynamics
  • Fuel Management
  • Data Processing
  • Energy

Publications


An overview of sustainable energy development by using cogeneration technology and opportunity for improving process

A.A. Salehi, M.GH-Maragheh,M.T. Mostaedi,R. Torkaman,M. Asadollahzadeh
Scientific Journals (ISI) DOI:10.1002/er.5742, 24 June 2020

Developing 3D neutron transport kernel for heterogeneous structures in an improved method of characteristic (MOC) framework

M.H. Porhemmat,K. Hadad,A.A. Salehi,A. Moghadam
Scientific Journals (ISI)127 (2020) 103442

Hydrogel materials as an emerging platform for desalination and the production of purified water, Separation & Purification Reviews

A.A. Salehi, M.GH-Maragheh, M.T. Mostaedi, R. Torkaman, M. Asadollahzadeh
Scientific Journals (ISI) DOI:10.1080/15422119.2020

Anew Monte Carlo approach for solution of the time dependent neutron transport equation based on nodal discretization to simulate the xenon oscillation with feedback

M. Ghaderi-Mazaher, A. A. Salehi, Nasser Vosoughi, et
Scientific Journals (ISI) 141 -107302 ,2020

A review on the Water-energy nexus for drinking water production from humid air

A.A. Salehi, M. Ghannadi Maragheh, M.T. Mostaedi, R. Torkaman, M. Asadollahzadeh, et
Scientific Journals (ISI)2019

A new approach for solution of time dependent neutron transport equation based on nodal discretization using MCNPX code with feedback

M. Ghaderi- Mazaher, A.A. Salehi, Naser Vosoughi, et
Scientific Journals (ISI), Annals of Nuclear energy, 133- 519-526 ,2019

Implementation of a dynamic Monte Carlo Method for Transient Analysis with Thermal-Hydraulic Feedback Using MCNPX Code

M. Ghaderi-Mazaher,A. A. Salehi,Nasser Vosoughi, et al
Scientific Journals (ISI) Accepted for publication, Annals of Energy, 130, pp-240-249 ,2019

A time dependent Mont Carlo approach for nuclear reactor analysis in a 3-D arbitrary geometry

M. Ghaderi-Mazaher,A.A. Salehi, Nasser Vosoughi, et al
Scientific Journals (ISI)115, pp-80-90 ,2019

Public ingestion exposure to 226Ra in Ramsar, Iran

9. N. Fathabadi,A. A. Salehi, K. Naddafi, M. R. Kardan M. Yunesian, R. Nabizadeh Nodehi, M.R. Deevband, M. Gooniband-Shooshtari
Scientific Journals (ISI) Journal of Environmental Radioactivity, Vol. 198, pp. 11-17,2019

Impact of integral burnable absorbers on SMART reactor behavior under normal and anomalous operational conditions

S. Kamalpour,A. A. Salehi,H. Khalafi, N. Mataji-Kojouri, Gh. Jahanfarnia
Scientific Journals (ISI)Progress in Nuclear Energy, Vol. 110, pp. 51-63 ,2019

The Potential impact of Fully Ceramic Microencapsulated (FCM) fuel on thermal hydraulic performance of SMART reactor

S. Kamalpour,A. A. Salehi, H. Khalafi, N. Mataji-Kojouri, Gh. Jahanfarnia
Scientific Journals (ISI) Nuclear Engineering and Design, Vol. 339, pp. 39-52 ,2018

Radioactivity Levels in the mostly local foodstuff consumed by residents of the high level natural radiation areas of Ramsar, Iran

N. Fathabadi, A. A. Salehi, K. Naddafi, M.R. Kardan M. Yunesian, R. Nabizadeh Nodehi, M.R. Deevband, M. Gooniband Shooshtari
Scientific Journals (ISI) Journal of Environmental Radioactivity, Vol. 169–170, pp. 209-213 ,2017

Analytical study of 226Ra activity concentration in market consuming foodstuffs of Ramsar, Iran

13. M. Gooniband-Shooshtari, M.R. Deevband, M. R. Kardan, N. Fathabadi,A. A. Salehi , K. Naddafi, M. Yunesian, R. Nabizadeh Nodehi, M. Karimi and S. S. Hosseini
Scientific Journals (ISI)Journal of Environmental Health Science & Eng., pp. 15-19, DOI:10.1186/s40201-017-0281-3, 2017

A sensitivity analysis of thermal lattices kinetic parameters with respect to the spectral weighting function using ultrafine BN method

V. F. Fallah, A. A. Salehi, N. Vosoughi, S. M. Ayyoubzadeh
Scientific Journals (ISI) Progress in Nuclear Energy 88, pp. 310-320,2016

Optimization of neutron energy-group structure in thermal lattices using ultrafine bilinear ad joint function

V. F. Fallah,A. A. Salehi , N. Vosoughi, M Akbari
Scientific Journals (ISI) Progress in Nuclear Energy 85, pp. 648-658,2015

Axial enrichment profile in advance nuclear energy power plant at supercritical-pressures

S. Tashakor, E. Zarifi,A. A. Salehi
Scientific Journals (ISI)Kern Technik, Vol. 80, No. 6, pp. 541-544, https://doi.org/10.3139/124.110544,2015

Variable moderation high performance light water reactor (VMHWR)

G. Jahanfarnia, S. Tashakor,A. A. Salehi, A. Abbaspour Tehrani-Fard
Scientific Journals (ISI) Annals of Nuclear Energy, Vol. 58, pp.1-5,2013

Thermal-hydraulic analysis of HPLWR fuel assembly cluster

S. Tashakor,A. A. Salehi , G. Jahanfarnia, A. Abbaspour Tehrani Fard
Scientific Journals (ISI) The Journal of Supercritical Fluids VOL. 77 pp. 91-99,2013

Neutronic analysis of HPLWR fuel assembly cluster

S. Tashakor,A. A. Salehi, G. Jahanfarnia, A. Abbaspour Tehrani Fard
Scientific Journals (ISI)Annals of Nuclear Energy, Vol. 50, pp. 38-43, 2012

Direct Discrete Method (DDM) and its Application to Neutron Transport Problems

N. Vosoughi, A. A. Salehi , M. Shahriari, M. Heshmatzede
Scientific Journals (ISI) Scientia Iranica, Vol. 14, Issue 1, pp. 78-85,2007

Discrete Formulation for Two Dimensional Multi Group Neutron Diffusion Equations

N. Vosoughi,A. A. Salehi , M. Shahriari
Scientific Journals (ISI)Annals of Nuclear Energy, Vol. 31, Issue 3. pp 231-253 ,2004

Neutron Flux Flattening in PWRs using Neural Network and fuel Management

M. Sadighi, S. Setayesh, A. A. Salehi
Scientific Journals (ISI) IEEE Transactions on Nuclear Science, Vol. 49, No. 3, pp. 1574-1578, June ,2002

PWR Fuel Management Optimization using Neural Network

M. Sadighi, S. Setayesh, A. A. Salehi
Scientific Journals (ISI)Annals of Nuclear Energy, Vol. 29 (1), pp. 41-51, 2002

Neutronic Aanlysis of HPLWR Fuel Assembly Cluster

S. Tashakor, , A. A. Salehi, G.J. Ahanfarnia, A. Abbaspour Tehrani Fard
International Conferences & Technical Reports The 6th Annual International Conference on Sustainable Development through Nuclear Research and Education May 22-24, 2013

Application of Direct Discrete method (DDm) to Multi-group Neutron Transport Problems

N. Vosoughi, , A. A. Salehi, M. Shahriari
International Conferences & Technical Reports International conference on Nuclear Engineering (ICONE-10), Tokyo, Japan, April 2003

Direct Discrete Method for Neutonic Calculations

N. Vosoughi, , A. A. Salehi, M. Shahriari
International Conferences & Technical Reports International Conference on Nuclear Engineering (ICONE-10), Washington U.S.A, April 2002.

PWR Fuel Management Optimization using Neural Network

4. M. Sadighi, S. Setayesh, A. A. Salehi
International Conferences & Technical ReportsProceeding of 10th International and 9th Annual Mechanical Engineering Conference, pp. 705-711, Guilan University, May 27-29, 2001

Monte Carlo Method for PGNAA of NaCl Solution Compound with Experimental Results at the NRC Research Reactor

N. M. Kojouri, A. A. Soltanieh, A.A. Salehi
International Conferences & Technical Reports 8th International Conference, Modern Trends in actibation Analysis, Physics Dept., Technical University of Vienna, (16-20 September 1991)

Use of Fast Reactor Methods to Generate Few Group Cross Sections for Thermal Reactor

H. Aminfar, M. J. Driscoll, A. A. Salehi
International Conferences & Technical Reports Proc. American Nuclear Society Topical Meeting, Gatlinburg, Tennessee, USA (April 10-12 1978)

Resonance region neutronics of unit cells in fast and thermal reactors

A. A. Salehi, M. J. Driscoll, and O. L. Deutsch
International Conferences & Technical Reports Massachusetts Inst. of Tech., Cambridge (USA). Dept. of Nuclear Engineering, DOI: 10.2172/5054274, (1977)

Few Pauses on Reactor physics

A. A. Salehi
Domestic Journals & Technical ReportsICTP, Italy (1994)

Evaluation of Dynamic Behavior of Bushehr Plant Using Simple Methods

M. Sadighi, A. A. Salehi
Domestic Journals & Technical Reports Accepted for Presentation in International Congress on Computational: Methods in Engineering, School of Engineering. Shiraz University, Shiraz, I.R. Iran (May 3-5 1993)

Development of an Equivalence Relation and a New Disadvantage Factor Applicable to both Fast and Thermal Energy Regions

A. A. Salehi
Domestic Journals & Technical Reports Iranian Journal of Science and Technology, Shiraz, I.R. Iran (1993)

A Thorough Technical report on the Bushehr Nuclear Power Plant

, A. A. Salehi . et al
Domestic Journals & Technical Reports submitted to Organization of Planning and Budget (1989)

A Program for Analyzing the Dynamic Behavior of CAN 11 Reactor Using Simple Models

A. A. Salehi
Domestic Journals & Technical Reports DYN, TN103288, ENACE, BS.AS. (July 1988)

Transient from Natural-U to LEU Fuelled Cores in the Argos

A. A. Salehi
Domestic Journals & Technical Reports PHWR-380 tn103588, ENACE, BS.AS. (October 1988)

A Survey of the Potential Geothermal Energy in Iran

A. A. Salehi et al
Domestic Journals & Technical Reports Tech Report No. 602.201, Ministry of Energy (1982)

A Survey of the Potential Hydroelectric in Iran

, A. A. Salehi et al
Domestic Journals & Technical ReportsTech. Report No. 401.01. Ministry of Energy (1982)

A Survey of the Potential Wind Energy in Iran

, A. A. Salehiet al
Domestic Journals & Technical ReportsTech. report No. 603.01, Ministry of Energy (1981)

A Survey of Fuel Cycle of the Bushehr Power Plant

11. A.A. Bakeshloo,, A. A. Salehi
Domestic Journals & Technical Reports Report Submitted to Atomic Energy Organization of Iran (1980)

12. Optimization of neutron energy – group structure in thermal lattices using ultrafine bilinear ad joint function

, A. A. Salehi
Domestic Journals & Technical Reports

A sensitivity analysis of thermal lattices kinetic parameters with respect to the spectral weighting function using ultrafine BN method.

, A. A. Salehi
Domestic Journals & Technical Reports

Use of Fast Reactor Methods to Generate Few Group Cross Sections for Thermal Reactor

H. Aminfar, M. J. Driscoll, A. A. Salehi
Domestic Journals & Technical Reports Proc. American Nuclear Society Topical Meeting, Gatlinburg, Tennessee, USA (April 10-12 1978)

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