Dr Omid Noorikalkhoran

2020

• Noorikalkhoran, O. and Gei, M. 2020. Evaluation of neutron radiation damage in zircaloy fuel clad of nuclear power plants: A study based on PKA and dpa calculations. Progress in Nuclear Energy 118, article number: 103079. (10.1016/j.pnucene.2019.103079)

2018

• Noorikalkhoran, O. and Gei, M. 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 20182018 26th International Conference on Nuclear Engineering: Thermal-Hydraulics and Safety Analyses, Vol. 6B. ASME pp. V06BT08A071-V06BT08A071., (10.1115/ICONE26-82635)

2017

• Noorikalkhoran, O. and Sevostianov, I. 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, O., 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, R., Noorikalkhoran, O. and Sadeghi, N. 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)

2016

• Noorikalkhoran, O., Shirani, A. S. and Ahangari, R. 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, O. and Shirani, A. 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.

2014

• Noorikalkhoran, O.et al. 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, O.et al. 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, O.et al. 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.et al. 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)

2013

• Rahgoshay, M. and Noorikalkhoran, O. 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)

2010

• Ahmadi, S. J., Noorikalkhoran, O. and Shirvani-Arani, S. 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)