Zobrazeno 1 - 10
of 17
pro vyhledávání: '"Omar Zerkak"'
Publikováno v:
Nuclear Engineering and Technology, Vol 50, Iss 3, Pp 356-367 (2018)
A series of tests dedicated to station blackout (SBO) accident scenarios have been recently performed at the Primärkreislauf-Versuchsanlage (primary coolant loop test facility; PKL) facility in the framework of the OECD/NEA PKL-3 project. These inve
Externí odkaz:
https://doaj.org/article/d20e6b24605948fa886e32a1905066bf
Autor:
Omar Zerkak, Durga Rao Karanki, Damar Canggih Wicaksono, Vinh N. Dang, Aaron Epiney, Sharif Rahman
Publikováno v:
Reliability Engineering & System Safety. 175:62-78
Dynamic Event Tree (DET) analysis allows for integrated deterministic and probabilistic safety assessment by coupling thermal-hydraulic system models with safety system and operator response models. It is a realistic but computationally challenging a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::28fed1918d478f624045b14fa2c2dd81
https://doi.org/10.1016/j.ress.2018.03.009
https://doi.org/10.1016/j.ress.2018.03.009
Publikováno v:
Nuclear Engineering and Technology, Vol 50, Iss 3, Pp 356-367 (2018)
A series of tests dedicated to station blackout (SBO) accident scenarios have been recently performed at the Primärkreislauf-Versuchsanlage (primary coolant loop test facility; PKL) facility in the framework of the OECD/NEA PKL-3 project. These inve
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2c8ca40da59ee746d2bf8f13788ad640
http://www.sciencedirect.com/science/article/pii/S1738573317305727
http://www.sciencedirect.com/science/article/pii/S1738573317305727
Autor:
N. García-Herranz, A. Sargeni, F. Fouquet, Y. Kozmenkov, S. Sánchez-Cervera, Y. Perin, F. Bernard, A. Sabater, P. Mala, Hakim Ferroukhi, D. Cuervo, Sören Kliem, J. Hadek, Omar Zerkak
Publikováno v:
Nuclear Engineering and Design
Nuclear Engineering and Design, Elsevier, 2017, 321, pp.8-25. ⟨10.1016/j.nucengdes.2017.05.028⟩
Nuclear Engineering and Design 321(2017), 8-25
Nuclear Engineering and Design, ISSN 0029-5493, 2017-09, Vol. 321
Archivo Digital UPM
Universidad Politécnica de Madrid
Nuclear Engineering and Design, Elsevier, 2017, 321, pp.8-25. ⟨10.1016/j.nucengdes.2017.05.028⟩
Nuclear Engineering and Design 321(2017), 8-25
Nuclear Engineering and Design, ISSN 0029-5493, 2017-09, Vol. 321
Archivo Digital UPM
Universidad Politécnica de Madrid
International audience; Within the NURESAFE project, a main steam line break benchmark has been defined and solved by codes integrated into the European code platform NURESIM. The paper describes the results of the calculations for this benchmark. Si
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::9f68182c14d7e498f006c1272f4df15a
https://doi.org/10.1016/j.nucengdes.2017.05.028
https://doi.org/10.1016/j.nucengdes.2017.05.028
Publikováno v:
Reliability Engineering & System Safety. 162:91-102
The coupling of plant simulation models and stochastic models representing failure events in Dynamic Event Trees (DET) is a framework used to model the dynamic interactions among physical processes, equipment failures, and operator responses. The int
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8af3ab0b224f313f2b391c83598428b7
https://doi.org/10.1016/j.ress.2017.01.015
https://doi.org/10.1016/j.ress.2017.01.015
Publikováno v:
Annals of Nuclear Energy. 102:190-199
With the goal to enhance the capability to perform best-estimate simulations of Light Water Reactors (LWRs) transients, with strong coupling between core neutronics and plant thermal-hydraulic, a coupling between TRACE and SIMULATE-3K (TS3K) was deve
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2a2e39859a78f7ac68ade80ad1803f32
https://doi.org/10.1016/j.anucene.2016.12.015
https://doi.org/10.1016/j.anucene.2016.12.015
Autor:
Omar Zerkak, A. Dohkane, Andreas Pautz, S. Bogetic, S. Canepa, Hakim Ferroukhi, Mathieu Hursin
Publikováno v:
Annals of Nuclear Energy. 101:559-575
The paper deals with the development of a TRACE/PARCS plenum to plenum model for the Swiss Boiling Water Reactor (BWR) Leibstadt (KKL), for cycle 19. It summarizes a verification of the model against an existing SIMULATE-3 model and a validation agai
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4465e78f387f6a3e237a230f878aee4e
https://doi.org/10.1016/j.anucene.2016.11.001
https://doi.org/10.1016/j.anucene.2016.11.001
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
Publikováno v:
Annals of Nuclear Energy. 84:225-233
The advanced numerical simulation of a realistic physical system typically involves multi-physics problem. For example, analysis of a LWR core involves the intricate simulation of neutron production and transport, heat transfer throughout the structu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::413b756781cf2feee71bcd886e0647c2
https://doi.org/10.1016/j.anucene.2015.01.019
https://doi.org/10.1016/j.anucene.2015.01.019
Autor:
Omar Zerkak, Hakim Ferroukhi
Publikováno v:
Annals of Nuclear Energy. 38:60-71
A Main Steam Line Break transient analysis for a Swiss operated Pressurized Water Reactor has been performed using the code RETRAN-3D, which included a 3-D core model applying a one-to-one correspondence between the thermal–hydraulic and the neutro
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3f9d9d847d897f561488e644c79bcf3b
https://doi.org/10.1016/j.anucene.2010.08.016
https://doi.org/10.1016/j.anucene.2010.08.016