Uncertainty propagation of fission product yields to nuclide composition and decay heat for a PWR UO2 fuel assembly

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Uncertainty propagation of fission product yields to nuclide composition and decay heat for a PWR UO2 fuel assembly. / Leray, Olivier; Fiorito, Luca; Rochman, D.; Ferroukhi, Hakim; Stankovskiy, Alexey ; Van den Eynde, Gert.

In: Progress in Nuclear Energy, Vol. 101, 11.2017, p. 486-495.

Research output: Contribution to journal › Article

Harvard

Leray, O, Fiorito, L, Rochman, D, Ferroukhi, H, Stankovskiy, A & Van den Eynde, G 2017, 'Uncertainty propagation of fission product yields to nuclide composition and decay heat for a PWR UO2 fuel assembly', Progress in Nuclear Energy, vol. 101, pp. 486-495. https://doi.org/10.1016/j.pnucene.2017.05.033

APA

Leray, O., Fiorito, L., Rochman, D., Ferroukhi, H., Stankovskiy, A., & Van den Eynde, G. (2017). Uncertainty propagation of fission product yields to nuclide composition and decay heat for a PWR UO2 fuel assembly. Progress in Nuclear Energy, 101, 486-495. https://doi.org/10.1016/j.pnucene.2017.05.033

Vancouver

Leray O, Fiorito L, Rochman D, Ferroukhi H, Stankovskiy A , Van den Eynde G. Uncertainty propagation of fission product yields to nuclide composition and decay heat for a PWR UO2 fuel assembly. Progress in Nuclear Energy. 2017 Nov;101:486-495. https://doi.org/10.1016/j.pnucene.2017.05.033

Author

Leray, Olivier ; Fiorito, Luca ; Rochman, D. ; Ferroukhi, Hakim ; Stankovskiy, Alexey ; Van den Eynde, Gert. / Uncertainty propagation of fission product yields to nuclide composition and decay heat for a PWR UO2 fuel assembly. In: Progress in Nuclear Energy. 2017 ; Vol. 101. pp. 486-495.

Bibtex - Download

@article{52f915a1d50b45e58a3a1974d9e9b2e6,

title = "Uncertainty propagation of fission product yields to nuclide composition and decay heat for a PWR UO2 fuel assembly",

abstract = "The assessment of the fission yield uncertainties on neutronic parameters is of great interest for criticality and spent fuel behavior studies. In this work, several fission yield perturbation methodologies are used to propagate the uncertainties for a PWR fuel assembly. Aside from the TENDL-2011 fission yields, a Generalized Least Square method is used on the JEFF-3.1.1 and the ENDF/B-VII.1 fission yields to generate correlations in agreement with the conservation equations. The branching ratios are also perturbed using this technique. Moreover the GEF code is employed to generate correlated fission yields from perturbed model parameters but also, coupled to a Bayesian process, to generate correlated fission yields for ENDF/B-VII.1. The resulting kinf uncertainty versus the exposure are assessed and discussed as well as nuclide density uncertainties at 60 GWd/tIHM and the decay heat uncertainty up to 105 days (274 years).",

keywords = "Fission yield perturbation, SHARK-X, GEF, SANDY, ENDF/B-VII.1, Decay Heat",

author = "Olivier Leray and Luca Fiorito and D. Rochman and Hakim Ferroukhi and Alexey Stankovskiy and {Van den Eynde}, Gert",

note = "Score=10",

year = "2017",

month = "11",

doi = "10.1016/j.pnucene.2017.05.033",

language = "English",

volume = "101",

pages = "486--495",

journal = "Progress in Nuclear Energy",

issn = "0149-1970",

publisher = "Elsevier",

}

RIS - Download

TY - JOUR

T1 - Uncertainty propagation of fission product yields to nuclide composition and decay heat for a PWR UO2 fuel assembly

AU - Leray, Olivier

AU - Fiorito, Luca

AU - Rochman, D.

AU - Ferroukhi, Hakim

AU - Stankovskiy, Alexey

AU - Van den Eynde, Gert

N1 - Score=10

PY - 2017/11

Y1 - 2017/11

N2 - The assessment of the fission yield uncertainties on neutronic parameters is of great interest for criticality and spent fuel behavior studies. In this work, several fission yield perturbation methodologies are used to propagate the uncertainties for a PWR fuel assembly. Aside from the TENDL-2011 fission yields, a Generalized Least Square method is used on the JEFF-3.1.1 and the ENDF/B-VII.1 fission yields to generate correlations in agreement with the conservation equations. The branching ratios are also perturbed using this technique. Moreover the GEF code is employed to generate correlated fission yields from perturbed model parameters but also, coupled to a Bayesian process, to generate correlated fission yields for ENDF/B-VII.1. The resulting kinf uncertainty versus the exposure are assessed and discussed as well as nuclide density uncertainties at 60 GWd/tIHM and the decay heat uncertainty up to 105 days (274 years).

AB - The assessment of the fission yield uncertainties on neutronic parameters is of great interest for criticality and spent fuel behavior studies. In this work, several fission yield perturbation methodologies are used to propagate the uncertainties for a PWR fuel assembly. Aside from the TENDL-2011 fission yields, a Generalized Least Square method is used on the JEFF-3.1.1 and the ENDF/B-VII.1 fission yields to generate correlations in agreement with the conservation equations. The branching ratios are also perturbed using this technique. Moreover the GEF code is employed to generate correlated fission yields from perturbed model parameters but also, coupled to a Bayesian process, to generate correlated fission yields for ENDF/B-VII.1. The resulting kinf uncertainty versus the exposure are assessed and discussed as well as nuclide density uncertainties at 60 GWd/tIHM and the decay heat uncertainty up to 105 days (274 years).

KW - Fission yield perturbation

KW - SHARK-X

KW - GEF

KW - SANDY

KW - ENDF/B-VII.1

KW - Decay Heat

UR - https://ecm.sckcen.be/OTCS/llisapi.dll?func=ll&objaction=overview&objid=35080472

U2 - 10.1016/j.pnucene.2017.05.033

DO - 10.1016/j.pnucene.2017.05.033

M3 - Article

VL - 101

SP - 486

EP - 495

JO - Progress in Nuclear Energy

JF - Progress in Nuclear Energy

SN - 0149-1970

ER -

ID: 5319735