International Course to Support Nuclear Licensing by User Training in the Areas of Scaling, Uncertainty, and 3D Thermal-Hydraulics/Neutron-Kinetics Coupled Codes: 3D S.UN.COP Seminars

Autor: Alessandro Petruzzi, Francesco D'Auria, Tomislav Bajs, Francesc Reventos, Yassin Hassan

Publikováno v: Science and Technology of Nuclear Installations, Vol 2008 (2008)

Thermal-hydraulic system computer codes are extensively used worldwide for analysis of nuclear facilities by utilities, regulatory bodies, nuclear power plant designers, vendors, and research organizations. The computer code user represents a source

Externí odkaz: https://doaj.org/article/e55f2b51c2674ae4a112cb40c6199cb9

SAPIUM: a generic framework for a practical and transparent quantification of thermal hydraulic code model input uncertainty

Autor: Jinzhao Zhang, Guillaume Damblin, Francesc Reventos, Mathieu Couplet, Jean Baccou, Nils Sandberg, Bertrand Iooss, Philippe Fillion, Takeshi Takeda, Alessandro Petruzzi, T. Skorek, Deog-Yeon Oh, Rafael Mendizábal

Publikováno v: Nuclear Science and Engineering
Nuclear Science and Engineering, 2020, 194, pp.721-736. ⟨10.1080/00295639.2020.1759310⟩
Nuclear Science and Engineering, Academic Press, 2020, 194, pp.721-736. ⟨10.1080/00295639.2020.1759310⟩

International audience; Uncertainty analysis (UA) is a key element in nuclear power plant (NPP) deterministic safety analysis using best-estimate thermal hydraulic codes and best estimate plus uncertainty (BEPU) methodologies. If forward uncertainty

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::019d4c82dcc9c210783d300b1f077489
https://hal.science/hal-03149294

Perfecting the use of hybrid models in scaling analysis

Autor: V. Martinez-Quiroga, Francesc Reventos, J. Freixa

Publikováno v: UPCommons. Portal del coneixement obert de la UPC
Universitat Politècnica de Catalunya (UPC)
Recercat. Dipósit de la Recerca de Catalunya
instname

Different methodologies devoted to qualify Nuclear Power Plant (NPP) system-code nodalizations rely on Kv-scaled calculations as an essential tool for their purpose. In the framework of Power-To-Volume strategy, a Kv-scaled calculation is a simulatio

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::29a225625709e831844727a66b364ce8
https://hdl.handle.net/2117/176828

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
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

Simulation of steam generator plugging tubes in a PWR to analyze the operating impact

Autor: Manuel Martin Ramos, Ismael Sol, Francesc Reventos, Patricia Pla, Miodrag Strucic

Publikováno v: Nuclear Engineering and Design. 305:132-145

A number of nuclear power plants (NPPs) with pressurized water reactors (PWR) in the world have replaced their steam generators (SG) due to degradation of the SG tubes caused by different problems. Several methods were attempted to correct the defect

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::493b864e050af8f15d0bafcbd2bf2183
https://doi.org/10.1016/j.nucengdes.2016.05.002