Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes – PREMIUM benchmark

Autor: Agnès de Crécy, Jinzhao Zhang, Damar Canggih Wicaksono, Victor Sanchez, J. Freixa, T. Skorek, Francesc Reventos, Yuri Shvestov, Deog Yeon Oh, Alexander Falkov, Rostislav Pernica, A. Kovtonyuk, Milos Kyncl, Torsti Alku, Fabrice Fouet, Alexey Gusev, Dong Li, Rafael Mendizábal, Christine Sarrette, Elsa de Alfonso, Omar Zerkak, Pierre Probst, Joona Kurki, Andreas Pautz, Wadim Jäger, Bub Dong Chung, Tran Tranh Tram, Jean Baccou, Xiaojing Liu, Alessandro Petruzzi

Publikováno v: Recercat. Dipósit de la Recerca de Catalunya
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UPCommons. Portal del coneixement obert de la UPC
Universitat Politècnica de Catalunya (UPC)
Skorek, T, de Crécy, A, Kovtonyuk, A, Petruzzi, A, Mendizábal, R, de Alfonso, E, Reventós, F, Freixa, J, Sarrette, C, Kyncl, M, Pernica, R, Baccou, J, Fouet, F, Probst, P, Chung, B D, Tram, T T, Oh, D Y, Gusev, A, Falkov, A, Shvestov, Y, Li, D, Liu, X, Zhang, J, Alku, T, Kurki, J, Jäger, W, Sánchez, V, Wicaksono, D, Zerkak, O & Pautz, A 2019, ' Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes : PREMIUM benchmark ', Nuclear Engineering and Design, vol. 354, 110199 . https://doi.org/10.1016/j.nucengdes.2019.110199
Nuclear Engineering and Design
Nuclear Engineering and Design, Elsevier, 2019, 354, pp.110199. ⟨10.1016/j.nucengdes.2019.110199⟩
Nuclear Engineering and Design, 2019, 354, pp.110199. ⟨10.1016/j.nucengdes.2019.110199⟩

International audience; PREMIUM (Post BEMUSE Reflood Models Input Uncertainty Methods) was an activity launched with the aim ofpushing forward the methods of quantification of physical model uncertainties in thermal-hydraulic codes. Thebenchmark PREM

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::034e92523802183d7d777b90e0a0b627
https://hdl.handle.net/2117/173446

Sensitivity Analysis by the Use of a Surrogate Model During Large Break LOCA on ZION Nuclear Power Plant With CATHARE-2 V2.5 Code

Autor: Fabrice Fouet, Pierre Probst

Publikováno v: Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications.

In nuclear safety, the Best-Estimate (BE) codes may be used in demonstration and licensing, provided that uncertainties are added to the relevant output parameters before comparing them with the acceptance criteria. The uncertainty of output paramete

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::4ff539d0727b9a67c3b9a64f93c1bf23
https://doi.org/10.1115/icone17-75661