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Investigating the Performance and safety features of Pressurized water reactors using the burnable poisons
Faculty
Science
Year:
2020
Type of Publication:
ZU Hosted
Pages:
10
Authors:
Sune Mohammad Reda Mohammed
Staff Zu Site
Abstract In Staff Site
Journal:
Annals of Nuclear Energy ELSEVIR
Volume:
107354
Keywords :
Investigating , Performance , safety features , Pressurized water
Abstract:
Investigating the performance and safety features of Pressurized water reactors (PWRs) using the burnable poisons (BPs) are evaluated in this paper. Modeling and simulating of PWR assembly from Vera core physics benchmark are carried out using the MCNPX code. The effect of using different burnable poisons (eight) on the neutronic parameters are studied. Moreover, the types of BPs either as integral burnable absorbers (IBAs) or as burnable poison rods (BPRs) are investigated. The effect of these poisons on the effective multiplication factor is the first parameter that simulated. Gadolinium oxide (Gd2O3) and Erbium oxide (Er2O3) are used as IBAs that mixed homogenously with uranium fuel. The results indicated that Erbium is more effective than Gadolinium due to the fast depletion of gadolinium that shortens the core life. Zirconium diboride (ZrB2), Lutetium Oxide (Lu2O3) and Protactinium Oxide (PaO2) are also investigated as IBAs that are used as coating the outer surface of fuel rod. The results demonstrated that Protactinium is more effective than other poisons. Moreover, the impact of Pyrex (SiO2-B2O3), WABA (Al2O3-B4C) and Hafnium di-boride (HfB2) are included and analyzed. Effective multiplication factor and beta effective are evaluated at the beginning of life of reactor operation. Finally, via the Pin by pin power distribution at BOC and EOC on the assembly level, maximum and minimum power values for the different cases are compared.
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Sune Mohammad Reda Mohammed, "Assessment study for multi-barrier system used in radioactive borate waste isolation based on Monte Carlo simulations", Applied Radiation and Isotopes, Volume 70, Issue 1, January 2012, Pages 99-102., 2012
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Sune Mohammad Reda Mohammed, "Comparative Study for Homogenous and Inhomogeneous Photon Dose Distribution from a High Dose Rate 192Ir Brachytherapy Source using MCNP5.", Arab Journal of Nuclear Science and Applications, 46(4), (165-175) 2013., 2013
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Sune Mohammad Reda Mohammed, "Calculation of the NEA C5G7 MOX benchmark with MCNP5.", Progress in Nuclear Energy 76, (244-254) 2014., 2014
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Sune Mohammad Reda Mohammed, "Reactivity Prediction Calculations for Infinite Arrays of PWR MOX Fuel Pin Cells using MCNP5 and WIMSD-5B.", J. Nucl. Energ. Sci. Power Generat. Technol., 2015, 4-2,, 2015
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Sune Mohammad Reda Mohammed, "Gamma Ray Shielding by a New Combination of Aluminum, Iron, Copper and Lead using MCNP5.", Arab Journal of Nuclear Science and Applications, 94 (4), (211-217) 2016., 2016
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