Zobrazeno 1 - 10
of 64
pro vyhledávání: '"Zoltán Hózer"'
Autor:
Róbert Farkas, Zoltán Hózer, Zoltán Kis, Erzsébet Perez-Feró, Márton Király, Márta Horváth, Tamás Novotny, Péter Szabó, Tamás Bubonyi
Publikováno v:
Nuclear Materials and Energy, Vol 40, Iss , Pp 101695- (2024)
A loss-of-coolant accident in a nuclear power plant was simulated in the CODEX-SLIM experiment. The electrically heated fuel rod bundle contained cladding material used at a VVER-440 power plant. The maximum temperature reached 900 °C and the experi
Externí odkaz:
https://doaj.org/article/0f461f47618f43708db5f1171a6e1971
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 9, Pp 2990-3002 (2021)
The mechanical interaction between the fuel pellet and the cladding tube of a nuclear fuel rod is a very important for safety studies as this phenomenon could lead to fuel failure and release of radioactivity. To investigate the ductility of cladding
Externí odkaz:
https://doaj.org/article/5bd30ebac41d4dd7a0f9d9eae095579f
Publikováno v:
Nuclear Engineering and Technology, Vol 50, Iss 7, Pp 1148-1153 (2018)
The Leaking Fuel Experiment test facility was designed to simulate the activity release from spent leaking fuel rods under steady state and transient conditions in the spent fuel pool. The experimental rig included an electrically heated fuel rod wit
Externí odkaz:
https://doaj.org/article/bf25b536e27044bc9b7d1637de8a07f0
Publikováno v:
Nuclear Engineering and Technology, Vol 50, Iss 3, Pp 425-431 (2018)
Different methods of axial and tangential testing and various sample geometries were investigated, and new test geometries were designed to determine the ultimate tensile strength of zirconium cladding tubes. The finite element method was used to mod
Externí odkaz:
https://doaj.org/article/6a5437803e7f4176b883164984e5c213
Akademický článek
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Autor:
Róbert Farkas, Zoltán Hózer, Imre Nagy, Nóra Vér, Péter Szabó, Márta Horváth, Pál Kostka, Gábor Lajtha
Publikováno v:
Progress in Nuclear Energy. 161:104720
Autor:
Emese Slonszki, Zoltán Hózer
Publikováno v:
SSRN Electronic Journal.
Autor:
Róbert Farkas, Zoltán Hózer, Imre Nagy, Nóra Vér, Péter Szabó, Márta Horváth, Pál Kostka, Gábor Lajtha
Publikováno v:
SSRN Electronic Journal.
Autor:
Róbert Farkas, Zoltán Hózer, Imre Nagy, Nóra Vér, Márta Horváth, Martin Steinbrück, Juri Stuckert, Mirco Grosse
Publikováno v:
Nuclear Engineering and Design, 396, 111884
The CODEX-AIT-3 experiment simulated an in-vessel air ingress scenario after failure of bottom head of a nuclear reactor. 1600 °C maximum temperature was reached with the electrically heated bundle and slow cool-down was applied at the end of the te
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::3fd41c19940daf6ed9162b49589d7bdc
https://publikationen.bibliothek.kit.edu/1000148900/149957349
https://publikationen.bibliothek.kit.edu/1000148900/149957349
Autor:
T. Novotny, E. Perez-Feró, Róbert Farkas, M. Horváth, Péter Holecz, Zoltán Kis, N. Vér, Imre Nagy, Boglárka Maróti, Márton Király, György Auguszt, Zoltán Hózer, György Gémes, László Szentmiklósi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::953b2021c4d85188f494a6853003a68e
https://doi.org/10.1520/stp162220190010
https://doi.org/10.1520/stp162220190010