Quantification of the differences introduced by nuclear fuel cycle simulators in advanced scenario studies

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Quantification of the differences introduced by nuclear fuel cycle simulators in advanced scenario studies. / Villacorta Skarbeli, Aris; Merino Rodriguez, Ivan; Alvarez Velarde, Francisco; Hernandez Solis, Augusto; Van den Eynde, Gert.

In: Annals of nuclear energy, Vol. 137, 107160, 30.10.2019, p. 1-9.

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Villacorta Skarbeli, A, Merino Rodriguez, I, Alvarez Velarde, F, Hernandez Solis, A & Van den Eynde, G 2019, 'Quantification of the differences introduced by nuclear fuel cycle simulators in advanced scenario studies', Annals of nuclear energy, vol. 137, 107160, pp. 1-9. https://doi.org/10.1016/j.anucene.2019.107160

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Villacorta Skarbeli, Aris ; Merino Rodriguez, Ivan ; Alvarez Velarde, Francisco ; Hernandez Solis, Augusto ; Van den Eynde, Gert. / Quantification of the differences introduced by nuclear fuel cycle simulators in advanced scenario studies. In: Annals of nuclear energy. 2019 ; Vol. 137. pp. 1-9.

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@article{d95f3fcfd1494dce8327028fbf835bd3,
title = "Quantification of the differences introduced by nuclear fuel cycle simulators in advanced scenario studies",
abstract = "Uncertainty propagation and quantification, when applied to the field of nuclear fuel cycle scenario studies, usually only considers a set of easily quantifiable input parameters, leaving out the effects of the modelling approaches. In order to extend the validity of these analyses, two different codes, ANICCA and TR_EVOL (developed respectively by SCKCEN and CIEMAT), have been benchmarked through a study of an advanced and realistic nuclear fuel cycle scenario with the aim of assessing the impact of the use of different tools in the fuel cycle scenario uncertainty quantification. Additionally, a classical uncertainty propagation analysis was done following the total Monte Carlo and sensitivity approaches in order to compare the system uncertainties with the dissimilarities due the simulators. Results shows that the impact of the fuel cycle simulators cannot be neglected for certain observables, and that their effects become relevant as the scenarios extends over time due their cumulative effect.",
keywords = "fuel cycle simulator, uncertainty quantification, trasmutation, advanced fuel cycle",
author = "{Villacorta Skarbeli}, Aris and {Merino Rodriguez}, Ivan and {Alvarez Velarde}, Francisco and {Hernandez Solis}, Augusto and {Van den Eynde}, Gert",
note = "Score=10",
year = "2019",
month = "10",
day = "30",
doi = "10.1016/j.anucene.2019.107160",
language = "English",
volume = "137",
pages = "1--9",
journal = "Annals of nuclear energy",
issn = "0306-4549",
publisher = "Elsevier",

}

RIS - Download

TY - JOUR

T1 - Quantification of the differences introduced by nuclear fuel cycle simulators in advanced scenario studies

AU - Villacorta Skarbeli, Aris

AU - Merino Rodriguez, Ivan

AU - Alvarez Velarde, Francisco

AU - Hernandez Solis, Augusto

AU - Van den Eynde, Gert

N1 - Score=10

PY - 2019/10/30

Y1 - 2019/10/30

N2 - Uncertainty propagation and quantification, when applied to the field of nuclear fuel cycle scenario studies, usually only considers a set of easily quantifiable input parameters, leaving out the effects of the modelling approaches. In order to extend the validity of these analyses, two different codes, ANICCA and TR_EVOL (developed respectively by SCKCEN and CIEMAT), have been benchmarked through a study of an advanced and realistic nuclear fuel cycle scenario with the aim of assessing the impact of the use of different tools in the fuel cycle scenario uncertainty quantification. Additionally, a classical uncertainty propagation analysis was done following the total Monte Carlo and sensitivity approaches in order to compare the system uncertainties with the dissimilarities due the simulators. Results shows that the impact of the fuel cycle simulators cannot be neglected for certain observables, and that their effects become relevant as the scenarios extends over time due their cumulative effect.

AB - Uncertainty propagation and quantification, when applied to the field of nuclear fuel cycle scenario studies, usually only considers a set of easily quantifiable input parameters, leaving out the effects of the modelling approaches. In order to extend the validity of these analyses, two different codes, ANICCA and TR_EVOL (developed respectively by SCKCEN and CIEMAT), have been benchmarked through a study of an advanced and realistic nuclear fuel cycle scenario with the aim of assessing the impact of the use of different tools in the fuel cycle scenario uncertainty quantification. Additionally, a classical uncertainty propagation analysis was done following the total Monte Carlo and sensitivity approaches in order to compare the system uncertainties with the dissimilarities due the simulators. Results shows that the impact of the fuel cycle simulators cannot be neglected for certain observables, and that their effects become relevant as the scenarios extends over time due their cumulative effect.

KW - fuel cycle simulator

KW - uncertainty quantification

KW - trasmutation

KW - advanced fuel cycle

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/36034439

U2 - 10.1016/j.anucene.2019.107160

DO - 10.1016/j.anucene.2019.107160

M3 - Article

VL - 137

SP - 1

EP - 9

JO - Annals of nuclear energy

JF - Annals of nuclear energy

SN - 0306-4549

M1 - 107160

ER -

ID: 5711034