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Bafrani, Hamidreza Arab, Noori-kalkhoran, Omid, Gei, Massimiliano, 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
Item availability restricted. |
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Noorikalkhoran, Omid and Gei, Massimiliano 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. ASME, V06BT08A071-V06BT08A071. 10.1115/ICONE26-82635 |
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Noorikalkhoran, Omid 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 |
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Noorikalkhoran, Omid, 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 |
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Ahangari, Rohollah, Noorikalkhoran, Omid 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 |
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Noorikalkhoran, Omid, 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 |
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Hamedani, A, Noorikalkhoran, Omid 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. |
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Noorikalkhoran, Omid, 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 |
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Noorikalkhoran, Omid, 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 |
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Noorikalkhoran, Omid, 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 |
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Safarzadeh, O., Zolfaghari, A., Zangian, M. and Noorikalkhoran, Omid 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 |
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Rahgoshay, Mohammad and Noorikalkhoran, Omid 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 |
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Ahmadi, Seyed Javad, Noorikalkhoran, Omid 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 |
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