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Utilizing even Plutonium Isotopes as burnable absorbers for controlling the reactivity and power distribution in Pressurized Water Reactors
Faculty
Science
Year:
2024
Type of Publication:
ZU Hosted
Pages:
Authors:
Elsayed Saied Abdelfattah Moustafa
Staff Zu Site
Abstract In Staff Site
Journal:
Progress in nuclear energy Elsevier Ltd
Volume:
Keywords :
Utilizing even Plutonium Isotopes , burnable absorbers
Abstract:
In this paper, a new approach is proposed for controlling the reactivity and power distribution in pressurized water reactor cores without the implementation of burnable absorbers. This approach depended on the homogeneous mixing of uranium oxide with even plutonium isotopes; Pu-238, Pu-240, and Pu-242. Three Plutonium fuels; (99% UO2 + 1% Pu-238), (99% UO2 + 1% Pu-240), and (98% UO2 + 0.5% Pu-238 + 1% Pu-240 + 0.5% Pu-242) were simulated using the MCNPX 2.7 code. The three plutonium fuels are compared with the other three erbium fuels; (99.9% UO2 + 0.1% 167Er2O3), (99.74% UO2 + 0.26% 167Er2O3), and (99.61% UO2 + 0.39% 167Er2O3), which are taken as reference fuels. The weight percent of UO2, plutonium isotopes and enriched erbium is adjusted to provide the same initial reactivity. This is important for holding a fair comparison between the two fuel types. The simulation demonstrated that even plutonium isotopes, like enriched erbium, can improve reactor safety parameters. It was found that Pu-240 added fuel can suppress the initial reactivity by 27% and extend the fuel cycle by 6.9% compared to the conventional UO2. The reason for fuel cycle extension is due to the production of Pu-241. Meanwhile, Pu-238 and Pu-even added fuels provide suppressing the initial keff by 13% and 35% and shortening the fuel cycle by 2.7% and 21%, respectively compared to the reference UO2 fuel. Moreover, the fuel temperature coefficient (FTC), moderator temperature coefficient (MTC) and void reactivity coefficient (VRC) of Plutonium fuels are found to more negative than those of erbium fuels at the later stages of burnup because of the spectrum hardening resulting from Pu-239 production.
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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