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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:
Elsayed Saied Abdelfattah Moustafa
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.
Author Related Publications
Elsayed Saied Abdelfattah Moustafa, "Full core analysis of IRIS reactor by using MCNPX", Applied Radiationand Isotopes, 2016
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Elsayed Saied Abdelfattah Moustafa, "Comparison of MCNPX/WIMS-D5 BurnupCalculation with SAS2H/KENO-v for the IRIS Reactor", Arab Journal of Nuclear Science and Applications, 2016
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Elsayed Saied Abdelfattah Moustafa, "Fuel burnup analysis for IRIS reactor using MCNPX and WIMS-D5 codes", PERGAMON-ELSEVIER SCIENCE LTD, 2016
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Elsayed Saied Abdelfattah Moustafa, "feasibility Study of thorium-plutonium Mixed oxide Assembly in Light Water Reactors", nature research, 2019
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Elsayed Saied Abdelfattah Moustafa, "ANALYSIS OF NEUTRONIC PARAMETERS OF A STANDARD PWR ASSEMBLY BY MCNPX CODE", Egyptian society of applied science, 2018
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