Zobrazeno 1 - 10
of 66
pro vyhledávání: '"Mirco Große"'
Autor:
Mirco Grosse, Felix Boldt, Michel Herm, Conrado Roessger, Juri Stuckert, Sarah Weick, Daniel Nahm
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 3, Pp 824-831 (2024)
In order to investigate the occurring processes during long-term dry storage of spent fuel assemblies, a joined project called SPIZWURZ, between the Karlsruhe Institute of Technology and the Gesellschaft für Anlagen-und Reaktorsicherheit (GRS), was
Externí odkaz:
https://doaj.org/article/966589df94094fa6b4460b7db8602ddc
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:
Applied Sciences, Vol 11, Iss 13, p 5775 (2021)
In situ neutron radiography experiments can provide information about diffusive processes and the kinetics of chemical reactions. The paper discusses requirements for such investigations. As examples of the zirconium alloy Zircaloy-4, the hydrogen di
Externí odkaz:
https://doaj.org/article/98c3fa57aebc4bdaa95f42624cf5f287
Publikováno v:
Journal of Nuclear Materials. 583:154538
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::dd79df2596a99d62b090699fed569c89
https://doi.org/10.1016/j.jnucmat.2023.154538
https://doi.org/10.1016/j.jnucmat.2023.154538
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0b478ba8049c44068e3da0a5aca8cc0a
https://doi.org/10.1016/j.jnucmat.2023.154433
https://doi.org/10.1016/j.jnucmat.2023.154433
Publikováno v:
Coatings; Volume 12; Issue 7; Pages: 875
Single-rod oxidation and quench experiments at very high temperatures in steam atmosphere were conducted with advanced, nuclear grade SiCf/SiC CMC cladding tube segments. A transient experiment was performed until severe local degradation of the samp
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=multidiscipl::addb8b12ae649e83be461aa1f3a9709b
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
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::4bdab484d6a89a753f8d4b10bda044ff
https://doi.org/10.14311/app.2020.28.0008
https://doi.org/10.14311/app.2020.28.0008
Autor:
Junkai Liu, Martin Steinbrueck, Mirco Große, Ulrike Stegmaier, Chongchong Tang, Di Yun, Jianqiao Yang, Yanguang Cui, Hans Jürgen Seifert
Publikováno v:
SSRN Electronic Journal.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e39f0804ab72ac4700259f2c3e36cf36
https://doi.org/10.2139/ssrn.4040784
https://doi.org/10.2139/ssrn.4040784
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