Zobrazeno 1 - 10
of 30
pro vyhledávání: '"L. Perneczky"'
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2012 (2012)
The PMK-2 facility is a full-pressure thermal-hydraulic model of the primary and partly the secondary circuit of the VVER-type units of Paks NPP. The facility was the first integral-type facility for VVERs. The PMK-2 was followed later by the PACTEL
Externí odkaz:
https://doaj.org/article/10d417c2842a457f91afa0af4abaceca
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2012 (2012)
The PMK-2 facility is a full-pressure thermal-hydraulic model of the primary and partly the secondary circuit of the VVER-type units of Paks NPP. The facility was the first integral-type facility for VVERs. The PMK-2 was followed later by the PACTEL
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::bbf0383108f0c974c85f2e258314beee
https://doi.org/10.1155/2012/780472
https://doi.org/10.1155/2012/780472
Autor:
E. Frühwirth, M. Wallerberger, L. Perneczky, Friedrich Aumayr, R. E. Olson, J. Schweinzer, A. Veiter, K. Igenbergs
The introduction of gases like nitrogen or neon for cooling the edge region of magnetically confined fusion plasmas has triggered a renewed interest in state selective cross sections necessary for plasma diagnostics by means of charge exchange recomb
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::44039c1560433bf3e5a9932a0ef33eff
http://arxiv.org/abs/1112.3513
http://arxiv.org/abs/1112.3513
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:
Experimental Thermal and Fluid Science. 4:36-43
The analysis of postulated accidents in nuclear power plants is carried out by computer codes that must be validated by experimental results. Experiments were performed on the PMK-NVH facility, a scaled-down model of the primary circuit of the Paks n
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e66fd08952b46215700ff0df15b1952d
https://doi.org/10.1016/0894-1777(91)90019-n
https://doi.org/10.1016/0894-1777(91)90019-n
Autor:
I. Tóth, Horst-Michael Prasser, Gy. Ézsöl, Jochen Zschau, A. Böttger, Gabor Baranyai, A. Guba, L. Perneczky
Publikováno v:
Kerntechnik 69(2004)4, 167
The paper presents the results of a thermal hydraulic experiment conducted at the PMK-2 test facility in the frame of the IMPAM-VVER project. The test was dedicated to a scenario assuming a loss-of-coolant event dur-ing the cool-down phase of the pla
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::cab73861f93a825a9f73c75f5d7c2abb
https://www.hzdr.de/publications/Publ-6545-1
https://www.hzdr.de/publications/Publ-6545-1
Publikováno v:
Magyar sebeszet. 54(5)
The authors present the results of 85 redo operations, which were performed in the 3rd Surgical Department of Semmelweis University and the Surgical Department of St. Borbála Hospital in Tatabánya. The period under survey lasted for five years from
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=pmid________::913fb7fb3867085caf0390135981f338
https://pubmed.ncbi.nlm.nih.gov/11723732
https://pubmed.ncbi.nlm.nih.gov/11723732
Akademický článek
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Publikováno v:
Experimental Thermal and Fluid Science. 7:134
One of the key means of increasing the safety of nuclear power plants is to ensure the prevention of accidents which could lead to core damage or even to core melt. If we look at the severity range, there is a group of accident sequences with a relat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1478e705f2b62508f4255086ae344bfc
https://doi.org/10.1016/0894-1777(93)90135-6
https://doi.org/10.1016/0894-1777(93)90135-6