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DC Field | Value | Language |
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dc.citation.conferencePlace | US | - |
dc.citation.endPage | 2754 | - |
dc.citation.startPage | 2746 | - |
dc.citation.title | 2019 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019 | - |
dc.contributor.author | Hursin, Mathieu | - |
dc.contributor.author | Park, Jinsu | - |
dc.contributor.author | Kim, Wonkyeong | - |
dc.contributor.author | Siefman, Daniel | - |
dc.contributor.author | Perret, Gregory | - |
dc.contributor.author | Vasiliev, Alexander | - |
dc.contributor.author | Rochman, Dimitri | - |
dc.contributor.author | Pautz, Andreas | - |
dc.contributor.author | Ferroukhi, Hakim | - |
dc.contributor.author | Lee, Deokjung | - |
dc.date.accessioned | 2024-02-01T00:05:52Z | - |
dc.date.available | 2024-02-01T00:05:52Z | - |
dc.date.created | 2020-01-29 | - |
dc.date.issued | 2019-08-25 | - |
dc.description.abstract | This paper presents an improved uncertainty quantification method for the validation of CASMO-5 on the spent fuel reactivity worth experiments of the LWR-PROTEUS Phase II program. For this method, we modeled with CASMO-5 the spent fuel reactivity worth measurement in the PROTEUS research reactor and the prior irradiation of the fuel in a Swiss nuclear power plant. We propagated the nuclear data uncertainties coming from cross-sections and fission yields in both fuel irradiations and reactivity worth experiment models using the SHARK-X tool. The fission yield and cross-section uncertainties have similar contributions to the uncertainty of the reactivity worth prediction. The reactivity worth probability distribution is non-normal because of the non-normal distribution of the perturbed fission yield data produced by the GEF code. The reactivity worth predictions obtained with CASMO-5 are very accurate for various moderating conditions and for all exposure conditions, even for burnup higher than 100 MWd/kg. Finally, we estimated the effects of the irradiation history specifications as well as various sources of nuclear data uncertainties on the relative reactivity worth uncertainty for a subset of the burnt fuel samples. The uncertainties due to the irradiation history specifications appear to be negligible. Scale-6.2, ENDF/B-VII.1 and JEFF-3.3 cross-sections uncertainty lead to consistent uncertainty estimates while the source of fission yield input uncertainty strongly affects the magnitude of the output. | - |
dc.identifier.bibliographicCitation | 2019 International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2019, pp.2746 - 2754 | - |
dc.identifier.scopusid | 2-s2.0-85075396203 | - |
dc.identifier.uri | https://scholarworks.unist.ac.kr/handle/201301/79355 | - |
dc.language | 영어 | - |
dc.publisher | American Nuclear Society | - |
dc.title | Uncertainty quantification of LWR-PROTEUS phase II experiments using CASMO-5 | - |
dc.type | Conference Paper | - |
dc.date.conferenceDate | 2019-08-25 | - |
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