Open Access
Issue |
EPJ Web Conf.
Volume 247, 2021
PHYSOR2020 – International Conference on Physics of Reactors: Transition to a Scalable Nuclear Future
|
|
---|---|---|
Article Number | 15011 | |
Number of page(s) | 8 | |
Section | Sensitivity & Uncertainty Methods | |
DOI | https://doi.org/10.1051/epjconf/202124715011 | |
Published online | 22 February 2021 |
- G. Rimpault, D. Plisson, J. Tommasi, R. Jacqmin, D. Verrier, and D. Biron. The ERANOS Code and Data System for Fast Reactor Neutronic Analyses. Physor 2002, (November), 2002. [Google Scholar]
- J. Leppänen, M. Pusa, T. Viitanen, V. Valtavirta, and Toni Kaltiaisenaho. The Serpent Monte Carlo code: Status, development and applications in 2013. Annals of Nuclear Energy, 82:142–150, 2015. [Google Scholar]
- M. Aufiero, M. Martin, and M. Fratoni. xGPT: Extending Monte Carlo Generalized Perturbation Theory capabilities to continuous-energy sensitivity functions. Annals of Nuclear Energy, 96:295–306, 2016. [Google Scholar]
- N. Abrate, M. Aufiero, S. Dulla, and L. Fiorito. Nuclear Data Uncertainty Quantification in Molten Salt Reactors with xGPT. In Proceedings of the ANS International Conference M&C2019, Portland, OR, August 25-29 2019. [Google Scholar]
- R. Bonifetto, S. Dulla, P. Ravetto, L. Savoldi Richard, and R. Zanino. A full-core coupled neutronic/thermalhydraulic code for the modeling of lead-cooled nuclear fast reactors. Nuclear Engineering and Design, 261:85–94, aug 2013. [Google Scholar]
- G. Grasso, C. Petrovich, D. Mattioli, C. Artioli, P. Sciora, D. Gugiu, G. Bandini, E. Bubelis, and K. Mikityuk. The core design of ALFRED, a demonstrator for the European lead-cooled reactors. Nuclear Engineering and Design, 278:287–301, 2014. [CrossRef] [Google Scholar]
- D. Rochman, A. J. Koning, S. C. Van Der Marck, A. Hogenbirk, and C. M. Sciolla. Nuclear data uncertainty propagation: Perturbation vs. Monte Carlo. Annals of Nuclear Energy, 38(5):942–952, 2011. [Google Scholar]
- Dan G Cacuci. Sensitivity & Uncertainty Analysis, Volume I: Theory. CRC Press, Boca Raton, 2003. [Google Scholar]
- R E Macfarlane, Contributing Authors, D W Muir, R M Boicourt, A C Kahler, J L Conlin, and W Haeck. The NJOY Nuclear Data Processing System, Version 2016. Technical report, 2018. [Google Scholar]
- D. Rochman, A.J. Koning, J.Ch. Sublet, M. Fleming, E. Bauge, S. Hilaire, P. Romain, B. Morillon, H. Duarte, S. Goriely, S.C. van der Marck, H. Sjöstrand, S. Pomp, N. Dzysiuk, O. Cabellos, H. Ferroukhi, and A. Vasiliev. The TENDL library: Hope, reality and future. EPJ Web of Conferences, 146:02006, 2017. [EDP Sciences] [Google Scholar]
- L. Fiorito, G. Žerovnik, A. Stankovskiy, G. Van den Eynde, and P. E. Labeau. Nuclear data uncertainty propagation to integral responses using SANDY. Annals of Nuclear Energy, 101:359–366, 2017. [Google Scholar]
- G F Nallo, N Abrate, S Dulla, Ravetto P., and Valerio D. Neutronic benchmark of the FRENETIC code for the multiphysics analysis of lead fast reactors. The European Physical Journal Plus, 123, 2020. [Google Scholar]
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