Zobrazeno 1 - 10
of 27
pro vyhledávání: '"I. Trosztel"'
Publikováno v:
Kerntechnik. 82:461-467
For calculation of the radiological consequences of Large Break Loss of Coolant (LBLOCA) events, a set of various computer codes modeling the corresponding physical processes, disciplines and their appropriate subsequent data exchange are necessary.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d211ecb66bd660f76fd42fe01232b948
https://doi.org/10.3139/124.110819
https://doi.org/10.3139/124.110819
Autor:
A. Vimi, Péter Szabó, Zoltán Hózer, Róbert Farkas, N. Vér, M. Kunstár, I. Trosztel, Imre Nagy
Publikováno v:
Nuclear Engineering and Design. 317:51-58
The CODEX-COOL experimental series was carried out in order to evaluate the effect of ballooning and pellet relocation in hexagonal bundles on the coolability of fuel rods after a LOCA event. The effects of blockage geometry, coolant flowrate, initia
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::15b84fecaf70c651ea3c434ba0cf79b0
https://doi.org/10.1016/j.nucengdes.2017.03.030
https://doi.org/10.1016/j.nucengdes.2017.03.030
Publikováno v:
Kerntechnik. 80:373-378
Homogeneous boron dilution scenarios in a VVER-440 reactor were analyzed using the coupled KIKO3D-ATHLET code. The scenarios are named “homogeneous” because of the very slow dilution caused by a rupture in the heat exchanger of the makeup system.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::43d3ee471de994a632f6828b45879d48
https://doi.org/10.3139/124.110512
https://doi.org/10.3139/124.110512
Autor:
H. György, I. Trosztel
Publikováno v:
Kerntechnik. 78:362-370
Severe accident – if no mitigation action is taken – leads to core melt. An effective severe accident management strategy can be the external reactor pressure vessel cooling for corium localization and stabilization. For some time discussion was
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2a38e3631a8e634bc8b87628eec32376
https://doi.org/10.3139/124.110380
https://doi.org/10.3139/124.110380
Publikováno v:
Progress in Nuclear Energy. 52:190-196
The dynamic core behavior of the HPLWR (High Performance Light Water Reactor) concept (Schulenberg, 2006), which is the European version of the GEN4 Supercritical Water Cooled Reactors (SCWR) was investigated in case of RIA (Reactivity Initiated Acci
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4aff99186c50b1786dd909c49bf5bb1a
https://doi.org/10.1016/j.pnucene.2009.06.005
https://doi.org/10.1016/j.pnucene.2009.06.005
Publikováno v:
Journal of Nuclear Engineering and Radiation Science. 2
The aim of the Supercritical Water Reactor - Fuel Qualification Test (SCWR-FQT) Euratom-China collaborative project is to design an experimental facility for qualification of fuel for the supercritical water-cooled reactor. The facility is intended t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3a63a0aa5d68945cb8bfe73aec18b134
https://doi.org/10.1115/1.4030933
https://doi.org/10.1115/1.4030933
Publikováno v:
Annals of Nuclear Energy. 30:93-120
A three-dimensional reactor dynamics program—KIKO3D—for coupled neutron kinetics and thermohydraulics calculation of VVER type pressurized water reactor cores has been developed and benchmarked. For solution of the time dependent neutronic equati
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::84377979431c24b13c6c5977eb99a224
https://doi.org/10.1016/s0306-4549(02)00043-9
https://doi.org/10.1016/s0306-4549(02)00043-9
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
Publikováno v:
12th International Conference on Nuclear Engineering, Volume 3.
In the deterministic safety analysis codes are required in order to provide evaluations of potential nuclear plant accidents. In the fields of the core transient behaviour, the computer codes have achieved a high degree of realistic modelling. Nevert
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7a177b843726a7ed06fa9bd7e2cf636a
https://doi.org/10.1115/icone12-49300
https://doi.org/10.1115/icone12-49300
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