Research output: Contribution to journal › Article
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
}
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