Zobrazeno 1 - 10
of 52
pro vyhledávání: '"C. Koehly"'
Publikováno v:
Fusion Engineering and Design, 192, Artkl.Nr.: 113753
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::2de3b65fc28e192983c486f206be2066
https://publikationen.bibliothek.kit.edu/1000158259/150966627
https://publikationen.bibliothek.kit.edu/1000158259/150966627
Publikováno v:
Fusion Engineering and Design. 193:113752
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::44d1076192f1bb4b235c9c8ec39ad5ab
https://doi.org/10.1016/j.fusengdes.2023.113752
https://doi.org/10.1016/j.fusengdes.2023.113752
Akademický článek
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Akademický článek
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Publikováno v:
Fusion Engineering and Design. 136:7-11
Thermohydraulic measurements in liquid metal test blanket modules for ITER require reliable sensors for detection of temperature and magnetohydrodynamic properties of the flow such as the distribution of electric potential. The latter one can be dire
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cc632883b8a347ae367373c3601dfd41
https://doi.org/10.1016/j.fusengdes.2017.12.004
https://doi.org/10.1016/j.fusengdes.2017.12.004
Publikováno v:
Fusion Engineering and Design. 127:168-172
Liquid metal magnetohydrodynamic (MHD) flows in a scaled mock-up of a Helium cooled lead lithium blanket have been investigated experimentally in the MEKKA laboratory at the Karlsruhe Institute of Technology. The test section consists of 8 breeder un
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ec5556d44326b3ab41ac3df0cece9d50
https://doi.org/10.1016/j.fusengdes.2018.01.007
https://doi.org/10.1016/j.fusengdes.2018.01.007
Publikováno v:
Nuclear Fusion. 61:096037
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8b5d730426d139f39a83fac51e02a525
https://doi.org/10.1088/1741-4326/ac18dc
https://doi.org/10.1088/1741-4326/ac18dc
Publikováno v:
Fusion Engineering and Design
New manufacturing methods for the production of key components for nuclear fusion reactors by selective laser melting (SLM) are currently under investigation at Karlsruhe Institute of Technology. SLM offers great potential compared to conventional ma
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::46c5bb4a671f99a59acc3e7461628905
Autor:
Joerg Rey, Francisco Hernandez, Alexander Felde, Ludek Stratil, Reinhard Niewöhner, Frederik Arbeiter, C. Koehly, Sebastian Ruck, Heiko Neuberger
Publikováno v:
Fusion Engineering and Design
Different manufacturing routes are investigated at the KIT INR for the realization of First Walls (FW) for nuclear fusion components, such as the ITER Test Blanket Module (TBM) and DEMO Breeding Blankets (BB) for the Helium Cooled Pebble Bed (HCPB) B
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::60864764daf1964d48d2b0beb29f35c4
Publikováno v:
Fusion Science and Technology
Fusion science and technology, 75 (8), 1010-1015
Fusion science and technology, 75 (8), 1010-1015
The water-cooled lead lithium (WCLL) blanket is one of the European concepts for a Demonstration nuclear fusion reactor (DEMO). The spatial distribution of the water-cooling pipes inside th...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::5c0882e1ad2abf3687bceed4c41e8aa9