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Study of neutronic characteristics for the VVER reactor assembly with five various burnable poisons using MCNPX code
Faculty
Science
Year:
2020
Type of Publication:
ZU Hosted
Pages:
Authors:
Sune Mohammad Reda Mohammed
Staff Zu Site
Abstract In Staff Site
Journal:
Progress in Nuclear Energy ELSEVIR
Volume:
Keywords :
Study , neutronic characteristics , , VVER reactor assembly
Abstract:
The present work investigates the neutronic characteristics of VVER reactor assembly with various burnable poisons. The MCNPX code is used to design VVER-1000 LEU Assembly model. At first gadolinium oxide (Gd2O3) as integral burnable absorber is used, the results are compared with the results of the reference benchmark. Different fuels (uranium oxide, thorium oxide and thorium plutonium oxide) and five various burnable poisons are used in the study. Gadolinium Oxide (Gd2O3) and Erbium Oxide (Er2O3) are used together in the same assembly as IBAs that are mixed homogenously with 30 uranium fuel rods and Dysprosium Titanite (Dy2O3–TiO2) is coated the fuel rod with 0.001 cm thickness. Also, Iridium Oxide (IrO2) used in guide tube as BPR and finally Minor Actinides are used as both IBAs or BPRs. A number of parameters are determined at BOL such as thermal neutron flux, axial power distribution and pin power distribution. Also, four physical parameters are studied, Keff, βeff, MTC and FTC. The burnup calculation is performed for VVER-1200. The comparison of the multiplication factor variation with depletion (for 730 days) illustrated that Iridium Oxide in Th–F assembly has a faster rate of depletion than other Burnable absorbers. Using Iridium Oxide shortens the core life time due to the transformation process of Ir-191 to Ir-192. Moreover, the concentration of actinides for the different assemblies at EOC were discussed. In addition, the effect of using BPs in different fuel assemblies on the concentration of 135Xe and 149Sm production are also performed.
Author Related Publications
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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