Zobrazeno 1 - 10
of 86
pro vyhledávání: '"Martin Steinbrück"'
Publikováno v:
Acta Polytechnica CTU Proceedings, Vol 28, Pp 8-14 (2020)
The investigations in this paper deal with the Cr-Ni alloy. The material has been recently proposed as a potential ATF concept, primarily due to its behaviour under high-temperature oxidation. A set of experiments to determine the melting point and d
Externí odkaz:
https://doaj.org/article/29a4e49412d74fa58ee93e2695cba154
Publikováno v:
Nuclear Engineering and Technology, Vol 50, Iss 2, Pp 237-245 (2018)
Potential air ingress scenarios during accidents in nuclear reactors or spent fuel pools have raised the question of the influence of air, especially of nitrogen, on the oxidation of zirconium alloys, which are used as fuel cladding tubes and other s
Externí odkaz:
https://doaj.org/article/59cc7cc1008d4095af113534f09ba043
Autor:
Chongchong Tang, Mirco Karl Grosse, Pavel Trtik, Martin Steinbrück, Michael Stüber, Hans Jürgen Seifert
Publikováno v:
Acta Polytechnica, Vol 58, Iss 1, Pp 69-76 (2018)
Hydrogen uptake by nuclear fuel claddings during normal operation as well as loss of coolant during design basis and severe accidents beyond design basis has a high safety relevance because hydrogen degrade the mechanical properties of the zirconium
Externí odkaz:
https://doaj.org/article/eefd3178c06e44e48b6b024a5e803fae
Autor:
Jan Škarohlíd, Petr Ashcheulov, Radek Škoda, Andrew Taylor, Radim Čtvrtlík, Jan Tomáštík, František Fendrych, Jaromír Kopeček, Vladimír Cháb, Stanislav Cichoň, Petr Sajdl, Jan Macák, Peng Xu, Jonna M. Partezana, Jan Lorinčík, Jana Prehradná, Martin Steinbrück, Irena Kratochvílová
Publikováno v:
Scientific Reports, Vol 7, Iss 1, Pp 1-14 (2017)
Abstract In this work, we demonstrate and describe an effective method of protecting zirconium fuel cladding against oxygen and hydrogen uptake at both accident and working temperatures in water-cooled nuclear reactor environments. Zr alloy samples w
Externí odkaz:
https://doaj.org/article/ec4d9375ba5b4250993ce24e420597eb
Publikováno v:
Journal of Nuclear Materials. 583:154538
Autor:
Junkai Liu, Ruizhi Meng, Martin Steinbrück, Mirco Große, Ulrike Stegmaier, Chongchong Tang, Jianqiao Yang, Di Yun
Publikováno v:
Journal of Nuclear Materials, 573, Art.-Nr.: 154144
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::52dc8fb02e8eea18b49ddd2661281f91
https://publikationen.bibliothek.kit.edu/1000153248
https://publikationen.bibliothek.kit.edu/1000153248
Autor:
Peter Doyle, Juri Stuckert, Mirco Grosse, Martin Steinbrück, Andrew T. Nelson, Jason Harp, Kurt Terrani
Publikováno v:
Journal of Nuclear Materials. 580:154433
Publikováno v:
Acta polytechnica, 28, 8–14
Acta Polytechnica CTU Proceedings, Vol 28, Pp 8-14 (2020)
Acta Polytechnica CTU Proceedings, Vol 28, Pp 8-14 (2020)
The investigations in this paper deal with the Cr-Ni alloy. The material has been recently proposed as a potential ATF concept, primarily due to its behaviour under high-temperature oxidation. A set of experiments to determine the melting point and d
Publikováno v:
Coatings; Volume 12; Issue 2; Pages: 167
Elemental Cr/C/Al multilayers (stoichiometric ratio: 2:1:1) with and without a Cr overlayer have been synthesized on Zircaloy-4 substrates by magnetron sputtering. The effects of annealing temperatures (400 and 550 °C) on phase/microstructure format
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