| Issue |
EPJ Web Conf.
Volume 247, 2021
PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
|
|
|---|---|---|
| Article Number | 15017 | |
| Number of page(s) | 8 | |
| Section | Sensitivity & Uncertainty Methods | |
| DOI | https://doi.org/10.1051/epjconf/202124715017 | |
| Published online | 22 February 2021 | |
https://doi.org/10.1051/epjconf/202124715017
UNCERTAINTY ANALYSIS OF SUB-EXERCISES IN UAM-SFR BENCHMARK WITH THE MCS CODE
Department of Nuclear Engineering, Ulsan National Institute of Science and Technology 50 UNIST-gil, Ulsan, 44919, Republic of Korea
yunki.jo@unist.ac.kr
dosvutheam8@unist.ac.kr
mainhan@unist.ac.kr
hyunsuklee@unist.ac.kr
deokjung@unist.ac.kr
Published online: 22 February 2021
Uncertainty analysis in Modelling (UAM) for Design, Operation and Safety Analysis of Sodium-cooled Fast Reactors (SFRs) has been formed by OECD/NEA to assess the effect of nuclear data uncertainties on parameters of interest in SFR analysis. In this paper, sub-exercises of a medium 1000 MWth metallic core (MET-1000) and a large 3600 MWth oxide core (MOX-3600) are tested by a Monte Carlo code MCS to perform uncertainty analysis. Classical perturbation theory and generalized perturbation theory are used to calculate sensitivity coefficients. Uncertainty is calculated by multiplying the sensitivity coefficients and relative covariance matrix from ENDF/B-VII.1 library.
Key words: Uncertainty quantification / MCS / UAM-SFR benchmark
© The Authors, published by EDP Sciences, 2021
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