Safety margin and fuel cycle period enhancements of VVER-1000 nuclear reactor using water/silver nanofluid von Saadati, Hassan, Hadad, Kamal, Rabiee, Ataollah

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Conceptual design of a high neutron flux research reactor core with low enriched uranium fuel and low plutonium production von Rahimi, Ghasem, Nematollahi, MohammadReza, Hadad, Kamal, Rabiee, Ataollah

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Two-Phase Flow Field Simulation of Horizontal Steam Generators von Rabiee, Ataollah, Kamalinia, Amir Hossein, Hadad, Kamal

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Particle size and concentration effects on low energy X-ray attenuation in nanostructure and microstructure materials von Sarshough, Samira, Hadad, Kamal, Faghihi, Reza

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Enhanced radiation shielding with galena concrete von Hadad, Kamal, Majidi, Hosein, Sarshough, Samira

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Indoor radon variations in central Iran and its geostatistical map von Hadad, Kamal, Mokhtari, Javad

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VOC level control by ventilation improvement of Flexography printing room using CFD modeling von Kamal Hadad, Hamid Reza Eidi, Javad Mokhtari

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Monte Carlo evaluation of neutron irradiation damage to the VVER-1000 RPV von Ardekani, Seyed Fazel Ghazi, Hadad, Kamal

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Twofold application of nanofluids as the primary coolant and reactivity controller in a PWR reactor: Case study VVER-1000 in normal operation von Hadad, Kamal, Kowsar, Zahra

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High-pressure core meltdown and hydrogen generation during in-vessel and ex-vessel phases of VVER-1000 nuclear reactor and effect of heat structures von Soltanmohammadi, Saied, Rabiee, Ataollah, Hadad, Kamal

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Innovative HPIS regulation system enhancing reactor safety in SBLOCA for WWER-1000/V446 NPP von Mirzamohammadzadeh, Mohammad Hossein, Hadad, Kamal, Pirouzmand, Ahmad

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Evaluation of time dependent neutron transport algorithms using 2D modular ray tracing MOC von Ghaseminejad, Sahar, Hadad, Kamal, Porhemmat, Mohammadhadi, Rabiee, Ataollah

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Human error probability quantification for NPP post-accident analysis using Cognitive-Based THERP method von Ramezani, Ahmad, Nazari, Tooraj, Rabiee, Ataollah, Hadad, Kamal, Faridafshin, Mohammadjavad

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Innovative designed fuel pin of conceptual semi-heavy water research reactor with improved reactor safety von Rahimi, Ghasem, Hadad, Kamal, Nematollahi, Mohammadreza

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Reducing the loss of offsite power contribution in the core damage frequency of a VVER-1000 reactor by extending the house load operation period von Mohsendokht, Massoud, Hadad, Kamal, Jabbari, Massoud

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ANALOG COMPUTING FOR A NEW NUCLEAR REACTOR DYNAMIC MODEL BASED ON A TIME-DEPENDENT SECOND ORDER FORM OF THE NEUTRON TRANSPORT EQUATION von Pirouzmand, Ahmad, Hadad, Kamal, Suh, Kune Y.

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Dose assessment of radionuclides dispersion from Bushehr nuclear power plant stack under normal operation and accident conditions von Pirouzmand, Ahmad, Dehghani, Peyman, Hadad, Kamal, Nematollahi, Mohammadreza

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PCTRAN enhancement for large break loss of coolant accident concurrent with loss of offsite power in VVER-1000 simulation von Hadad, K., Esmaeili-Sanjavanmareh, M.

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VVER-1000 cross-section library generation for ORIGEN-II based on MCNP calculations von Hadad, Kamal, Nematolahi, Mohammadreza, Golestani, Amin

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Numerical study of single and two-phase models of water/Al2O3 nanofluid turbulent forced convection flow in VVER-1000 nuclear reactor von Hadad, Kamal, Rahimian, Aref, Nematollahi, M.R.

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