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Uncertainty quantification of neutronic parameters of light water reactor fuel cells with JENDL-4.0 covariance data

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Title: Uncertainty quantification of neutronic parameters of light water reactor fuel cells with JENDL-4.0 covariance data
Authors: Chiba, Go Browse this author →KAKEN DB
Tsuji, Masashi Browse this author
Narabayashi, Tadashi Browse this author
Keywords: uncertainty quantification
covariance data
generalized perturbation theory
Issue Date: 1-Jul-2013
Publisher: Taylor & Francis
Journal Title: Journal of Nuclear Science and Technology
Volume: 50
Issue: 7
Start Page: 751
End Page: 760
Publisher DOI: 10.1080/00223131.2013.788793
Abstract: Neutronic parameter uncertainty induced by nuclear data uncertainty is quantified for several light water reactor fuel cells composed of different combinations of fissile/fertile nuclides. The covariance data given in JENDL-4.0 are used as the nuclear data uncertainty, and uncertainty propagation calculations are carried out using sensitivity coefficients calculated with the generalized perturbation theory for burnup-related neutronic parameters. It is found that main contributors of nuclear data uncertainty to the neutronic parameter uncertainty are the uranium-238 capture cross section in a uranium-oxide fuel cell, and the plutonium-240 and plutonium-241 capture cross sections and fission spectrum of fissile plutonium isotopes in a uranium-plutonium mixed-oxide fuel cell. It is also found that thorium-232 capture cross section uncertainty is a dominant source of neutronic parameter uncertainty in thorium-uranium and thorium-plutonium mixed-oxide fuel cells. It should be emphasized that precise and detail information of component-wise uncertainties can be obtained by virtue of the adjoint-based sensitivity calculation methodology. Furthermore, cross-correlations are evaluated for each fuel cell, and strong correlations among the same parameters at the beginning of cycle and at the end of cycle and among different parameters are observed.
Rights: This is an Author's Accepted Manuscript of an article published in Journal of Nuclear Science and Technology 2013 © Taylor & Francis, available online at:
Type: article (author version)
Appears in Collections:工学院・工学研究院 (Graduate School of Engineering / Faculty of Engineering) > 雑誌発表論文等 (Peer-reviewed Journal Articles, etc)

Submitter: 千葉 豪

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