Testing the NURESIM platform on a PWR main steam line break benchmark

Autor: Kliem, S., Kozmenkov, Y., Hadek, J., Perin, Y., Fouquet, F., Bernard, F., Sargeni, A., Cuervo, D., Sabater, A., Sanchez-Cervera, S., Garcia-Herranz, N., Zerkak, O., Ferroukhi, H., Mala, P.

Publikováno v: In Nuclear Engineering and Design September 2017 321:8-25

Analysis of Oskarshamn-2 stability event using TRACE/SIMULATE-3K and comparison to TRACE/PARCS and SIMULATE-3K stand-alone

Autor: Dokhane, A., Judd, J., Gajev, I., Zerkak, O., Ferroukhi, H., Kozlowski, T.

Publikováno v: In Annals of Nuclear Energy April 2017 102:190-199

Steady-state CFD simulations of an EPR™ reactor pressure vessel: A validation study based on the JULIETTE experiments

Autor: Puragliesi, R., Zhou, L., Zerkak, O., Pautz, A.

Publikováno v: In Nuclear Engineering and Design 15 April 2016 300:41-56

PREMIUM, a benchmark on the quantification of the uncertainty of the physical models in the system thermal-hydraulic codes: methodologies and data review

Autor: Reventos, F., de Alfonso, A., (Coordinators), Mendizabal R., Zhang, J., Kovtonyuk, A., Dethioux, A., Janssens, M., Léna, C., Segurado, J., Liu, X., Dong, Li, Kyncl, M., Pernica, R., Kopecek, V., Meca, R., Kurki, J., Alku, T., de Crécy, A., Bazin, P., Probst, P., Baccou, J., Fouet, F., Barré, F., Skorek, T., Jaeger, W., Sánchez, V., Petruzzi, A., D'Auria, FRANCESCO SAVERIO, Chung, B-D, Heo, J. S., D-Y, Oh, Gusev, A., Falkov, A., Shvetsov, Y., Zerkak, O., Wicaksono, D., Amri, A., Kissane, M.

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=od______3728::4fd3f78fe4fe8429bf668f8547fd10cb
http://hdl.handle.net/11568/890462

Revisiting temporal accuracy in neutronics/T-H code coupling using the NURESIM LWR simulation platform

Autor: Zerkak, O., Gajev, I., Manera, A., Kozlowski, T., Gommlich, A., Zimmer, S., Kliem, S., Crouzet, N., Zimmermann, M.

Publikováno v: 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics, NURETH-14, 25.-30.09.2011, Toronto, Canada
14th International Topical Meeting on Nuclear Reactor Thermalhydraulics, NURETH-14, 25.-30.09.2011, Toronto, CanadaProceedings of the 14th International Topical Meeting on Nuclear Reactor Thermalhydraulics, paper 484

The first part of the paper reviews the different temporal coupling methodologies that are currently employed for the transient simulation of LWR cores. The second part shows preliminary results from the implementation of some suggested coupling impr

Externí odkaz: https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::78f689860ea619f055b6223a2385c65f
https://www.hzdr.de/publications/Publ-16127-1