Zobrazeno 1 - 10
of 56
pro vyhledávání: '"M. Daubner"'
Publikováno v:
Nuclear Engineering and Design. 330:225-240
Internal blockages in fuel rod bundles can be rather small and may have a negligible global effect on the flow rate in a fuel assembly, and yet they can still produce significant local hot spots potentially leading to clad failure. Within the Europea
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bd458152e23f25ab4e18c7aa5ec1c322
https://doi.org/10.1016/j.nucengdes.2018.01.034
https://doi.org/10.1016/j.nucengdes.2018.01.034
Akademický článek
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Autor:
D. Angeli, Y. Bartosiewicz, S. Bassini, F. Bertocchi, D. Castelliti, X. Cheng, M. Daubner, L. De Moerloose, J. De Ridder, J. Degroote, A. Del Nevo, I. Di Piazza, M. Duponcheel, S. Eckert, F. Fellmoser, N. Forgione, S. Franke, C. Geffray, A. Gerschenfeld, D. Grishchenko, W. Hering, R. Hu, W. Jäger, M. Jeltsov, G. Kennedy, L. Koloszar, K. Kööp, N. Krauter, P. Kudinov, P. Lorusso, R. Marinari, D. Martelli, E. Merzari, I. Mickus, V. Moreau, J. Oder, J. Pacio, A. Pesetti, P. Planquart, W.D. Pointer, M. Polidori, F. Roelofs, M. Rohde, D. Rozzia, A. Shams, C. Spaccapaniccia, E. Stalio, R. Stieglitz, M. Tarantino, J. Thomas, I. Tiselj, K. Van Tichelen, J. Vierendeels, T. Wetzel, T. Wondrak
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b5f268dcc319c0169770c5538c4ed2f3
https://doi.org/10.1016/b978-0-08-101980-1.09991-9
https://doi.org/10.1016/b978-0-08-101980-1.09991-9
Publikováno v:
Nuclear Engineering and Design. 371:110928
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::194056f62800acfd78399f283c29b291
https://doi.org/10.1016/j.nucengdes.2020.110928
https://doi.org/10.1016/j.nucengdes.2020.110928
Akademický článek
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Publikováno v:
Nuclear Engineering and Design. 301:111-127
An experimental campaign considering a 19-pin hexagonal rod bundle with wire spacers, cooled by forced-convective LBE was completed at the Karlsruhe Liquid Metal Laboratory (KALLA). In the frame of the European research project SEARCH (Safe Exploitat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6f6e30cb15f20b101028da46b9ff5f55
https://doi.org/10.1016/j.nucengdes.2016.03.003
https://doi.org/10.1016/j.nucengdes.2016.03.003
Autor:
M. Daubner, Mariano Tarantino, J. Pacio, Daniele Martelli, Thomas Wetzel, M. Angelucci, I. Di Piazza
A detailed safety assessment of innovative Generation IV reactor designs with heavy-liquid metal coolants, such as lead and lead-bismuth eutectic (LBE), requires an evaluation of the maximum core temperature in several postulated scenarios. Consideri
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::008ab09835456c9d4f6027dce9e4d11b
https://www.scopus.com/inward/record.uri?eid=2-s2.0-85056181342&doi=10.1115/ICONE26-82213&partnerID=40&md5=65d1addc1781174a576113cc69aef965
https://www.scopus.com/inward/record.uri?eid=2-s2.0-85056181342&doi=10.1115/ICONE26-82213&partnerID=40&md5=65d1addc1781174a576113cc69aef965
Autor:
K. Litfin, F. Fellmoser, Robert Stieglitz, M. Daubner, Th. Wetzel, Luca Marocco, J. Pacio, Simon Taufall
Publikováno v:
Nuclear Engineering and Design. 273:33-46
Heavy-liquid metals, such as lead and lead-bismuth eutectic (LBE), are prominent candidate coolants for advanced fast reactor concepts and accelerator-driven systems. The thermal-hydraulic behavior of these fluids in fuel-assembly-representative geom
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::349fabad38ebca399b35d0f2f21e012d
https://doi.org/10.1016/j.nucengdes.2014.02.020
https://doi.org/10.1016/j.nucengdes.2014.02.020