Zobrazeno 1 - 9
of 9
pro vyhledávání: '"Wadim Jäger"'
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
instname
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⟩
instname
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
https://hdl.handle.net/2117/173446
Autor:
Ivan Otic, Jure Oder, Wadim Jäger, Iztok Tiselj, Afaque Shams, Wolfgang Hering, Thomas Schaub
Publikováno v:
Nuclear Engineering and Design. 359:110460
The backward facing step geometry (BFS) is a representative geometry for sudden expansions in pipe, duct and channel flows. While this type of geometry by itself is not a part of engineering components, the flow separation and the accompanying flow f
Publikováno v:
Energy Conversion and Management. 91:93-100
In this paper a macroscopic continuum differential model of pin bundle flow is proposed and developed for computational fluid dynamics (CFD) simulations of a reactor core. Thereby the pin bundle flow is regarded as a porous medium flow that is charac
Publikováno v:
Advances in New Heat Transfer Fluids ISBN: 9781315368184
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8df10bcbb02799fd298212dfb6f7661e
https://doi.org/10.1201/9781315368184-12
https://doi.org/10.1201/9781315368184-12
Autor:
V. H. Sánchez Espinoza, Wadim Jäger
Publikováno v:
Scopus-Elsevier
This paper will provide results of an uncertainty and sensitivity study in order to calculate parameters of safety related importance like the fuel centerline temperature, the cladding temperature and the fuel assembly pressure drop of a lead-alloy c
Publikováno v:
Nuclear Engineering and Design. 241:2184-2203
This paper summarizes the activities of the TRACE code validation at the Institute for Neutron Physics and Reactor Technology related to supercritical water conditions. In particular, the providing of the thermo physical properties and its appropriat
Publikováno v:
Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems.
Due to the variety of existing physical models for the heat transfer and for the description of thermo physical properties, the modeling results of different users for the same design can be different. These discrepancies can be rather big and have t
Autor:
L. Koloszar, W. Guo, Bojan Niceno, A. Villa Ortiz, Djamel Lakehal, Sophia Buckingham, Ferry Roelofs, K. Van Tichelen, Enrico Stalio, Andrea Fregni, Yann Bartosiewicz, Thomas Schaub, Chidambaram Narayanan, Philippe Planquart, Afaque Shams, Matthieu Duponcheel, Diego Angeli, Iztok Tiselj, Jure Oder, Wadim Jäger
Publikováno v:
Scopus-Elsevier
Nuclear Engineering and Design, Vol. 366, p. 110570 (2020)
Nuclear Engineering and Design, Vol. 366, p. 110570 (2020)
This article reports the experimental and DNS database that has been generated, within the framework of the EU SESAME and MYRTE projects, for various low-Prandtl flow configurations in different flow regimes. This includes three experiments: confined
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::6a34632e669bc0071037fb5a36878b3f
http://www.scopus.com/inward/record.url?eid=2-s2.0-85072262440&partnerID=MN8TOARS
http://www.scopus.com/inward/record.url?eid=2-s2.0-85072262440&partnerID=MN8TOARS