Zobrazeno 1 - 10
of 18
pro vyhledávání: '"M. Barnak"'
Autor:
T. Hollands, M. Stempniewicz, M. Barnak, P. Vokac, D. Angelova, M. Behler, R. Dagan, Claudia López, Algirdas Kaliatka, G.L. Horvath, D.F. Da Cruz, Ivo Kljenak, P. Matejovic, B.S. Jäckel, O. Kotsuba, Giacomino Bandini, M. Matkovic, Martin Steinbrück, Yu. Vorobyov, Luis E. Herranz, V. Vileiniskis, F. Rocchi, O. Zhabin, Olivia Coindreau, R. Thomas, D.C. Visser, F. Alcaro, Terttaliisa Lind, K. Mancheva, S. Ederli, P. Drai
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2018, 120, pp.880-887. ⟨10.1016/j.anucene.2018.06.043⟩
Annals of Nuclear Energy, Elsevier Masson, 2018, 120, pp.880-887. ⟨10.1016/j.anucene.2018.06.043⟩
International audience; Spent fuel pools (SFPs) are large structures equipped with storage racks designed to temporarily storeirradiated nuclear fuel removed from the reactor. SFP severe accidents have long been considered ashighly improbable since t
Autor:
P Chatelard, J. Slaby, G Lajtha, M. Constantin, M. Barnak, N. Reinke, A. Ezzidi, P. Majumdar, V. Lombard
Publikováno v:
Annals of Nuclear Energy
Annals of Nuclear Energy, Elsevier Masson, 2014, 74 (C), pp.224-242. ⟨10.1016/j.anucene.2014.05.010⟩
Annals of Nuclear Energy, Elsevier Masson, 2014, 74 (C), pp.224-242. ⟨10.1016/j.anucene.2014.05.010⟩
International audience; Among the 43 organisations which joined the SARNET2 FP7 project from 2009 to 2013, 31 have been involved in the activities on the ASTEC code. This paper presents a synthesis of the main achievements that have been obtained on
Akademický článek
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Autor:
J. P. Van Dorsselaere, P Kostka, A Bujan, K Müller, P Matejovic, J Slaby, K. Neu, M Barnak, H.J. Allelein
Publikováno v:
Nuclear Engineering and Design. 221:95-118
The main objective of the European Validation of the Integral Code ASTEC (EVITA) project is to distribute the severe accident integral code Accident Source Term Evaluation Code (ASTEC) to European partners in order to apply the validation strategy is
Autor:
Yu.A. Zvonarev, Istvan Toth, Attila Aszódi, C. Vitanza, Gy. Hegyi, I. Trosztel, P. Junninen, V.L. Kobzar, Y Makihara, G.L. Horvath, Zoltán Hózer, M. Fogel, K. Trambauer, P Matejovic, J. Verpoorten, K.C. Wagner, Gábor Légrádi, V. Guillard, K. Pietarinen, N. Tricot, Ildiko´ Boros, E. Perez-Feró, A. Voltchek, A. Molnár, E. Slonszki, Imre Nagy, L. Perneczky, Cs. Győri, M. Barnak
Publikováno v:
Hózer, Z, Aszódi, A, Barnak, M, Boros, I, Fogel, M, Guillard, V, Győri, C, Hegyi, G, Horváth, G L, Nagy, I, Junninen, P, Kobzar, V, Légrádi, G, Molnár, A, Pietarinen, K, Perneczky, L, Makihara, Y, Matejovic, P, Perez-Ferò, E, Slonszki, E, Tóth, I, Trambauer, K, Tricot, N, Troszterl, I, Verpoorten, J, Vitanza, A, Voltchek, K, Wagner, K C & Zvonarev, Y 2010, ' Numerical analyses of an ex-core fuel incident : Results of the OECD-IAEA Paks Fuel Project ', Nuclear Engineering and Design, vol. 240, no. 3, pp. 538-549 . https://doi.org/10.1016/j.nucengdes.2009.09.031
Nuclear Engineering and Design
Nuclear Engineering and Design, 2010, 240 (3), pp.538-549. ⟨10.1016/j.nucengdes.2009.09.031⟩
Nuclear Engineering and Design
Nuclear Engineering and Design, 2010, 240 (3), pp.538-549. ⟨10.1016/j.nucengdes.2009.09.031⟩
The OECD-IAEA Paks Fuel Project was developed to support the understanding of fuel behaviour in accident conditions on the basis of analyses of the Paks-2 incident. Numerical simulation of the most relevant aspects of the event and comparison of the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::4a0c084d5b18b160b63b8dbed137d420
https://cris.vtt.fi/en/publications/177c13bb-ed03-4c84-b4e4-7d855dc4b801
https://cris.vtt.fi/en/publications/177c13bb-ed03-4c84-b4e4-7d855dc4b801
Autor:
Michael Buck, G. Guillard, G. Ratel, G. Paitz, M. Barnak, Giacomino Bandini, Wolfgang Hering, A. Stefanova, V. Koundy, Nicolas Tregoures, L. Godin-Jacqmin, P. Matejovic
Publikováno v:
Progress in Nuclear Energy
Progress in Nuclear Energy, 2010, 52 (1), pp.148-157. ⟨10.1016/j.pnucene.2009.09.008⟩
Progress in Nuclear Energy, 2010, 52 (1), pp.148-157. ⟨10.1016/j.pnucene.2009.09.008⟩
Within the SARNET network of excellence in the 6th Framework Programme of the European Commission, the severe accident integral code ASTEC, jointly developed by IRSN (France) and GRS (Germany), has been validated against international experiments to
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::52a6ca79682e9e1082a3d87077c69da7
https://hal.archives-ouvertes.fr/hal-02972633
https://hal.archives-ouvertes.fr/hal-02972633
Publikováno v:
Nuclear Engineering and Design
Nuclear Engineering and Design, 2009, 239 (7), pp.1345-1353. ⟨10.1016/j.nucengdes.2009.02.021⟩
Nuclear Engineering and Design, 2009, 239 (7), pp.1345-1353. ⟨10.1016/j.nucengdes.2009.02.021⟩
This paper summarizes the work done in the SARNET European Network of Excellence on Severe Accidents (6th Framework Programme of the European Commission) on the capability of the ASTEC code to simulate in-vessel corium retention (IVR). This code, joi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::1c30b940b8114c42c7aa31505c763b8c
https://hal.archives-ouvertes.fr/hal-02988578
https://hal.archives-ouvertes.fr/hal-02988578
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Akademický článek
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