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Number of items: 23.

Jain, Lakshay, Noori-kalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663, Powell, Lewis, Jones, Andrew, Aflyatunova, Daliya and Merk, Bruno 2024. Neutronics design of shutdown and control systems for a Zero Power Experiments of chloride-based molten salt fast reactor. PLoS ONE 19 (10) , e0309928. 10.1371/journal.pone.0309928
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Noorikalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663, Jain, Lakshay and Merk, Bruno 2024. On the use of a chloride or fluoride salt fuel system in advanced molten salt reactors, part 3; radiation damage. Energies 17 (19) , 4772. 10.3390/en17194772
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Kanik, Muhammet Enis, Noorikalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663, Gei, Massimiliano and Fernández-Cosials, Kevin 2024. 3D analysis of spray effect on long-term depressurization of VVER-1000 containment during LB-LOCA. Progress in Nuclear Energy 170 , 105127. 10.1016/j.pnucene.2024.105127

Noorikalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663, Jain, Lakshay, Powell, Lewis, Jones, Andrew, Aflyatunova, Daliya and Merk, Bruno 2024. On the employment of a chloride or floride salt fuel system in advanced molten salt reactors, Part 2; Core inventory, fuel burnup, and salt clean-up system. Energies 17 (6) , 1475. 10.3390/en17061475
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Kanik, Muhammet Enis, Noorikalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663, Fernández-Cosials, Kevin and Gei, Massimiliano 2023. 3D analysis of hydrogen distribution and its mitigation using passive autocatalytic recombiners (PARs) inside VVER-1000 containment. Energies 16 (18) , 6612. 10.3390/en16186612
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Noorikalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663, Litskevich, Dzianis, Detkina, Anna, Jain, Lakshay, Cartland-Glover, Gregory and Merk, Bruno 2022. On the employment of a chloride or fluoride salt fuel system in advanced molten salt reactors, part 1: thermophysical properties and core criticality. Energies 15 (23) , 8865. 10.3390/en15238865
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Kanik, Muhammet Enis, Noorikalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663, Fernández-Cosials, Kevin and Gei, Massimiliano ORCID: https://orcid.org/0000-0003-3869-7504 2022. Full scope 3D analysis of a VVER-1000 containment pressurization during a LB-LOCA by employing AutoCAD and GOTHIC code. Progress in Nuclear Energy 152 , 104376. 10.1016/j.pnucene.2022.104376
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Safarzadeh, Omid, Noori-kalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663, Gei, Massimiliano, Morini, Lorenzo ORCID: https://orcid.org/0000-0001-7155-5036 and Ahangari, Rohollah 2021. Full scope simulation of VVER-1000 blowdown source and containment pressurization in a LBLOCA by parallel coupling of TRACE and CONTAIN. Progress in Nuclear Energy 140 , 103897. 10.1016/j.pnucene.2021.103897
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Ramezani, Ahmad, Nazari, Tooraj and NooriKalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663 2021. A proposed improvement for the design of safety injection system in VVER-1000/V446 reactor. Progress in Nuclear Energy 137 , 103767. 10.1016/j.pnucene.2021.103767

Safarzadeh, Omid and Noorikalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663 2021. A fractional PID controller based on fractional point kinetic model and particle swarm optimization for power regulation of SMART reactor. Nuclear Engineering and Design 377 , 111137. 10.1016/j.nucengdes.2021.111137

Bafrani, Hamidreza Arab, Noori-kalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663, Gei, Massimiliano ORCID: https://orcid.org/0000-0003-3869-7504, Ahangari, Rohollah and Mirzaee, Mohammad Mahdi 2020. On the use of boundary conditions and thermophysical properties of nanoparticles for application of nanofluids as coolant in nuclear power plants; a numerical study. Progress in Nuclear Energy 126 , 103417. 10.1016/j.pnucene.2020.103417
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Noorikalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663 and Gei, Massimiliano ORCID: https://orcid.org/0000-0003-3869-7504 2018. Simulation of hydrogen distribution due to in-vessel severe accident in WWER-1000 NPP containment: a comparison of CONTAIN and MELCOR codes results. Presented at: 26th International Conference on Nuclear Engineering, London, UK, 22-26 Jul 2018. 2018 26th International Conference on Nuclear Engineering: Thermal-Hydraulics and Safety Analyses. , vol.6B ASME, V06BT08A071-V06BT08A071. 10.1115/ICONE26-82635

Noorikalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663 and Sevostianov, Igor 2017. Micromechanical modeling of neutron irradiation induced changes in yield stress and electrical conductivity of zircaloy. International Journal of Engineering Science 120 , pp. 119-128. 10.1016/j.ijengsci.2017.07.002

Noorikalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663, Ahangari, R. and Shirani, A. S. 2017. Development of a parallel processing couple for calculations of control rod worth in terms of burn-up in a WWER-1000 reactor. Kerntechnik 82 (1) , pp. 43-56. 10.3139/124.110605

Ahangari, Rohollah, Noorikalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663 and Sadeghi, Nahid 2017. Radiological dose assessment for the hypothetical severe accident of the Tehran Research Reactor and corresponding emergency response. Annals of Nuclear Energy 99 , pp. 272-278. 10.1016/j.anucene.2016.09.005

Noorikalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663, Shirani, Amir Saied and Ahangari, Rohollah 2016. Simulation of containment pressurization in a large break-loss of coolant accident using single cell and multicell models and CONTAIN code. Nuclear Engineering and Technology 48 (5) , pp. 1140-1153. 10.1016/j.net.2016.03.008

Hamedani, A, Noorikalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663 and Shirani, A.S. 2016. Evaluation of single heated channel and subchannel modelling on a nuclear once through steam generator (OTSG). Presented at: 12th International Conference on Heat Transfer, Fluid Mechanics and Thermodynamics, Costa de Sol, Spain, 11-13 July 2016. HEFAT 2016.

Noorikalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663, Minuchehr, Abdolhamid, Shirani, Amir saied and Rahgoshay, Mohammad 2014. Full scope thermal-neutronic analysis of LOFA in a WWER-1000 reactor core by coupling PARCS v2.7 and COBRA-EN. Progress in Nuclear Energy 74 , pp. 193-200. 10.1016/j.pnucene.2014.03.006

Noorikalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663, Rahgoshay, Mohammad, Minuchehr, Abdolhamid and Shirani, Amir Saied 2014. Analysis of thermal–hydraulic parameters of WWER-1000 containment in a large break LOCA. Annals of Nuclear Energy 68 , pp. 101-111. 10.1016/j.anucene.2014.01.009

Noorikalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663, Minuchehr, Abdolhamid, Akbari-Jeyhouni, Reza, Shirani, Amir Saied and Rahgoshay, Mohammad 2014. Simulation of rod ejection accident in a WWER-1000 Nuclear Reactor by using PARCS code. Annals of Nuclear Energy 65 , pp. 132-140. 10.1016/j.anucene.2013.11.003

Safarzadeh, O., Zolfaghari, A., Zangian, M. and Noorikalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663 2014. Pattern optimization of PWR reactor using hybrid parallel Artificial Bee Colony. Annals of Nuclear Energy 63 , pp. 295-301. 10.1016/j.anucene.2013.08.011

Rahgoshay, Mohammad and Noorikalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663 2013. Calculation of control rod worth and temperature reactivity coefficient of fuel and coolant with burn-up changes for VVRS-2MWth nuclear reactor. Nuclear Engineering and Design 256 , pp. 322-331. 10.1016/j.nucengdes.2012.08.033

Ahmadi, Seyed Javad, Noorikalkhoran, Omid ORCID: https://orcid.org/0000-0001-6540-1663 and Shirvani-Arani, Simindokht 2010. Synthesis and characterization of new ion-imprinted polymer for separation and preconcentration of uranyl (UO22+) ions. Journal of Hazardous Materials 175 (1-3) , pp. 193-197. 10.1016/j.jhazmat.2009.09.148

This list was generated on Thu Apr 24 07:45:39 2025 BST.


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