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Neutronic investigation of enriched gadolinium, natural gadolinium and Zirconium-erbium as burnable poisons in the advanced PWR assemblies by MCNPX code
Faculty
Science
Year:
2023
Type of Publication:
ZU Hosted
Pages:
Authors:
Elsayed Saied Abdelfattah Moustafa
Staff Zu Site
Abstract In Staff Site
Journal:
Radiation Physics and Chemistry Elsevier Ltd
Volume:
Keywords :
Neutronic investigation , enriched gadolinium, natural gadolinium
Abstract:
In Pressurized Water Reactors, burnable absorbers are implemented for controlling the excess reactivity and avoiding the high power peaking factor. A feasibility study was carried out for investigating the effect of enriched gadolinium (157Gd2O3), natural gadolinium (152 - 160Gd2O3) and Zirconium-Erbium (ZrEr2) as burnable absorbers on the safety parameters of advanced PWR assembly. Three poisoned assemblies are modeled and simulated by the well-known MCNPX code. To hold a fair comparison between these assemblies, the author adjusted the concentration of fissile materials and burnable absorbers in each assembly to provide approximately the same initial reactivity. The MCNPX simulation showed that the enriched gadolinium model achieved a number of advantages over Zirconium-Erbium as: 1) prolonging the fuel cycle length by 1.04%, 2) increasing the negativity of moderator temperature coefficient and fuel temperature coefficient by 10.3% and 9.3% at the BOL and this contributes to core safety, 3) minimizing residual reactivity penalty at the higher burnup steps and 4) more hardening of neutron spectrum at the BOL. On the other hand, the Zirconium – Erbium layer presented a number of benefits over enriched gadolinium as 1) reducing the peaking factor by 1.3%, 2.6% and 2% at 20, 30 and 50 GWd/ton, 2) increasing the reactivity worth by 1.6% at the BOL, 3) increasing the power flattening by 7.6% at the EOL, and this is considered an enormous economic benefit. Therefore, the modeling of enriched gadolinium and zirconium erbium in this study is suggested for improving the neutronic and safety parameters of PWR cores.
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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