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Hózer, Z
Az atomerõművek üzemanyaga
In: Mihály, KA; Lévai, P; Kormos, I; Kármán, T (eds.) Hazalátogatott Wigner Jenő
Bp, Hungary : Eötvös Lóránd Fizikai Társulat (2021) 407 p. pp. 350-355. , 6 p.
Publication:32761401 Admin approved Core Chapter in Book (Chapter ) Scientific
Chapter (Chapter in Book) | Scientific[32761401] [Admin approved]
12.
Barsy, E ; Hózer, Z
A Zr-1%Nb ötvözet magas hőmérsékletű oxidációjának modellezése anyagvizsgálati módszerek alapján
ANYAGVIZSGÁLÓK LAPJA : 3 pp. 36-41. , 6 p. (2021)
Teljes dokumentum
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Article (Journal Article) | Scientific[32759627] [Approved]
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Hózer, Zoltán ; Nagy, Imre ; Farkas, Róbert ; Vér, Nóra ; Horváth, Márta ; Novotny, Tamás ; Perez-Feró, Erzsébet ; Király, Márton ; Kis, Zoltán ; Maróti, Boglárka et al.
Experimental Simulation of the Behavior of E110 Claddings under Accident Conditions Using Electrically Heated Bundles
In: Yagnik, Suresh K.; Motta, Arthur T.* Zirconium in the Nuclear Industry: 19th International Symposium
ASTM International (2021) pp. 813-832. Paper: STP162220190010 , 20 p.
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Romanenko, A. ; Agócs, E. ; Hózer, Z. ; Petrik, P. ; Serényi, M.
In-situ Ellipsometry on the Oxidation of Zirconium at Medium Temperatures
In: Sergey, Y. Yurish (eds.) Proceedings of the 4th International Conference on Optics, Photonics and Lasers (OPAL' 2021)
Barcelona, Spain : IFSA (2021) pp. 138-139. , 2 p.
REAL Google scholar hash
Publication:32604145 Validated Core Chapter in Book (Conference paper ) Scientific
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15.
Kiraly, M ✉ ; Horvath, M ; Nagy, R ; Ver, N ; Hozer, Z
Segmented mandrel tests of as-received and hydrogenated WWER fuel cladding tubes
NUCLEAR ENGINEERING AND TECHNOLOGY 53 : 9 pp. 2990-3002. , 13 p. (2021)
DOI WoS Scopus
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Groma, I ; Szenthe, I ; Odor, E ; Joni, B ; Zilahi, G ; Dankhazi, Z ; Ribarik, G ; Hozer, Z
Evolution of dislocation microstructure in irradiated Zr alloys determined by X-ray peak profile analysis
JOURNAL OF APPLIED CRYSTALLOGRAPHY 54 : 1 pp. 280-286. , 7 p. (2021)
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Barsy, E ; Szabo, P ; Kulacsy, K ; Hozer, Z
The non-uniform high-temperature oxidation of Zr-1%Nb cladding - A numerical model
PROGRESS IN NUCLEAR ENERGY 133 Paper: 103613 , 12 p. (2021)
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Ševeček, M. ; Krejčí, J. ; Chalupová, A. ; Kabátová, J. ; Manoch, F. ; Kočí, J. ; Cvrček, L. ; Tang, C. ; Steinbrűck, M. ; Grosse, M. et al.
Round robin exercise of the candidate ATF cladding materials within the IAEA ACTOF project
In: 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019
ANS (2020) pp. 283-290. , 8 p.
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Szenthe, I ; Gillemot, F ; Horvath, M ; Hozer, Z
Neutron Irradiation of Zirconium Alloys in the Budapest Research Reactor
IOP CONFERENCE SERIES: MATERIALS SCIENCE AND ENGINEERING 903 Paper: 012052 , 7 p. (2020)
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Hozer, Z ; Novotny, T ; Perez-Fero, E ; Horvath, M ; Csordas, AP ; Szabo, P ; Illes, L ; Schyns, M ; Delville, R ; Kim, D et al.
Development of new cladding types for nuclear fuel
IOP CONFERENCE SERIES: MATERIALS SCIENCE AND ENGINEERING 903 Paper: 012004 , 8 p. (2020)
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2024-04-27 13:04