Zobrazeno 1 - 10
of 54
pro vyhledávání: '"M. Jerab"'
Autor:
R. Vardai, T. Lummerstorfer, C. Pretschuh, M. Jerabek, M. Gahleitner, B. Pukanszky, K. Renner
Publikováno v:
eXPRESS Polymer Letters, Vol 13, Iss 3, Pp 223-234 (2019)
The impact resistance of polypropylene (PP)/wood composites was improved either by the traditional approach of adding an elastomer or by the use of poly(ethylene terephthalate) (PET) fibers. Composites were prepared with various elastomer and PET fib
Externí odkaz:
https://doaj.org/article/4ff3c5e1b89a4f47817bda1febec4984
Autor:
M. De Angeli, P. Tolias, C. Conti, D. Ripamonti, F. Ghezzi, C. Arnas, J. Irby, M. Jerab, B. LaBombard, S. Lecci, G. Maddaluno
Publikováno v:
Nuclear Materials and Energy, Vol 28, Iss , Pp 101045- (2021)
Magnetic dust collected from multiple fusion devices (FTU, Alcator C-Mod, COMPASS) that feature different plasma-facing components (PFCs) and toroidal magnetic fields has been analyzed by means of the X-ray diffraction technique aiming to investigate
Externí odkaz:
https://doaj.org/article/cb870ad455ec4f59b3359c1ea78bf4cd
Autor:
R. Dejarnac, J. Horacek, M. Hron, M. Jerab, J. Adamek, S. Atikukke, P. Barton, J. Cavalier, J. Cecrdle, M. Dimitrova, E. Gauthier, M. Iafrati, M. Imrisek, A. Marin Roldan, G. Mazzitelli, D. Naydenkova, A. Prishvitcyn, M. Tomes, D. Tskhakaya, G. Van Oost, J. Varju, P. Veis, A. Vertkov, P. Vondracek, V. Weinzettl
Publikováno v:
Nuclear Materials and Energy, Vol 25, Iss , Pp 100801- (2020)
Power handling experiments with a special liquid metal divertor module based on the capillary porous system technology were performed in the tokamak COMPASS. The performance of two metals (Li and LiSn alloy) were tested for the first time in a divert
Externí odkaz:
https://doaj.org/article/39ecacf10354486ea8238d048ce335f5
Publikováno v:
Nuclear Materials and Energy, Vol 25, Iss , Pp 100809- (2020)
To overcome the erosion of the plasma-facing materials (PFMs) inside a fusion reactor, liquid metals such as lithium or tin are being explored as potential PFMs in fusion reactors due to their several advantages such as self-repair or high-power exha
Externí odkaz:
https://doaj.org/article/ecc9a5d00e0e49788ff4f1ef791afb1d
Autor:
J. Horacek, R. Dejarnac, J. Cecrdle, D. Tskhakaya, A. Vertkov, J. Cavalier, P. Vondracek, M. Jerab, P. Barton, G. van Oost, M. Hron, V. Weinzettl, D. Sestak, S. Lukes, J. Adamek, A. Prishvitsin, M. Iafratti, Y. Gasparyan, Y. Vasina, D. Naydenkova, J. Seidl, E. Gauthier, G. Mazzitelli, M. Komm, J. Gerardin, J. Varju, M. Tomes, S. Entler, J. Hromadka, R. Panek
Publikováno v:
Nuclear Materials and Energy, Vol 25, Iss , Pp 100860- (2020)
Two small liquid metal targets based on the capillary porous structure were exposed to the divertor plasma of the tokamak COMPASS. The first target was wetted by pure lithium and the second one by a lithium-tin alloy, both releasing mainly lithium at
Externí odkaz:
https://doaj.org/article/230c13f0b42d4d68ad26ca6a897fb8df
Akademický článek
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Autor:
A. Weckmann, P. Petersson, J. Varju, M. Jerab, J. Horacek, J. Adamek, P. Vondracek, E. Fortuna, M. Hron, M. Rubel
Publikováno v:
Fusion Engineering and Design. 179:113118
Autor:
Olivier Février, Martin Hron, M. Sos, M. Bernert, L. Kripner, Matthias Komm, S. S. Henderson, Martin Imrisek, D. Mancini, D. Naydenkova, M. Morbey, Petra Bilkova, P. Bohm, Radomir Panek, Jordan Cavalier, D. Brida, J. Adamek, Petr Vondracek, M. Jerab
Publikováno v:
Nuclear Fusion
Nuclear Fusion, 61(3):036016. Institute of Physics
Nuclear Fusion, 61(3):036016. Institute of Physics
Substantial power dissipation in the edge plasma is required for the safe operation of ITER and next-step fusion reactors, otherwise unmitigated heat fluxes at the divertor plasma-facing components (PFCs) would easily exceed their material limits. Tr
Autor:
M. Farnik, Andre Torres, J. Blocki, I. Hanak, M. Tomes, Miglena Dimitrova, I. Duran, Jakub Bielecki, F. Prochazka, J. Fang, D. Zaloga, P. Barton, G. Cunningham, Ondrej Ficker, Jozef Varju, Martin Hron, Pavel Turjanica, Jacek Swierblewski, J. Horacek, V. Yanovskiy, Martin Imrisek, M. Kral, M. Sos, J. Gerardin, Han Zhang, P. Boocz, Matthias Komm, Robert Ellis, Jan Prevratil, J. Adamek, N. Isernia, M. Balazsova, O. Hronova, D. Fridrich, T. Majer, Marek Scholz, P. Chappuis, J. Svoboda, Petr Vondracek, O. Bogar, Slavomir Entler, V. Balner, V. Veselovsky, J. Krbec, L. Kripner, N. Patel, M. Mohelnik, F. Jaulmes, A. Zak, A. Brooks, M. Jerab, D. Tskhakaya, Dariusz Bocian, Fabio Villone, K. Bogar, D. Naydenkova, Radomir Panek, E. Matveeva, Vladimir Kindl, P. Junek, Jordan Cavalier, A. Herrmann, M. Varavin, Peter Titus, M. Peterka, Eva Macusova, I. Borodkina, I. Nemec, A. Havranek, A. Casolari, J. Zelda, J. Burant, K. Kovarik, J. Hromadka, I. Mysiura, Przemysław Wąchal, S. Fukova, G. Zadvitskiy, Grzegorz Tracz, R. Dejarnac, J. Zajac, Jan Reboun, Vladimir Weinzettl, M. Tadros, K. Mikszuta-Michalik, Tomas Markovic, K. Patocka, Rafal Ortwein, D. Sestak, Josef Havlicek, P. Hacek, A. Podolnik, V. Scalera, M. Dudak, Petra Bilkova, P. Bohm, T. Todd
Publikováno v:
Fusion Engineering and Design
COMPASS Upgrade is a new medium size, high magnetic field tokamak (R = 0.9 m, Bt = 5 T, Ip = 2 MA) currently under design in the Czech Republic. It will provide unique capabilities for addressing some of the key challenges in plasma exhaust physics,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::e0a96c4d899bed8b4691350d07b62c53
https://hdl.handle.net/21.11116/0000-0008-4119-321.11116/0000-0008-411B-1
https://hdl.handle.net/21.11116/0000-0008-4119-321.11116/0000-0008-411B-1
Autor:
Panagiotis Tolias, Bruce Lipschultz, Brian LaBombard, D.L. Rudakov, D. Ripamonti, M. De Angeli, Giorgio Maddaluno, M. Jerab, C. Arnas, J. H. Irby, Francesco Ghezzi, C.P. Chrobak, Claudia Conti
Publikováno v:
Fusion Engineering and Design
Fusion Engineering and Design, 2021, 166, pp.112315. ⟨10.1016/j.fusengdes.2021.112315⟩
Fusion Engineering and Design, Elsevier, 2021, 166, pp.112315. ⟨10.1016/j.fusengdes.2021.112315⟩
Fusion engineering and design 166 (2021): 112315-1–112315-6. doi:10.1016/j.fusengdes.2021.112315
info:cnr-pdr/source/autori:De Angeli M.; Ripamonti D.; Ghezzi F.; Tolias P.; Conti C.; Arnas C.; Jerab M.; Rudakov D.L.; Chrobak C.P.; Irby J.; LaBombard B.; Lipschultz B.; Maddaluno G./titolo:Cross machine investigation of magnetic tokamak dust: Morphological and elemental analysis/doi:10.1016%2Fj.fusengdes.2021.112315/rivista:Fusion engineering and design/anno:2021/pagina_da:112315-1/pagina_a:112315-6/intervallo_pagine:112315-1–112315-6/volume:166
Fusion Engineering and Design, 2021, 166, pp.112315. ⟨10.1016/j.fusengdes.2021.112315⟩
Fusion Engineering and Design, Elsevier, 2021, 166, pp.112315. ⟨10.1016/j.fusengdes.2021.112315⟩
Fusion engineering and design 166 (2021): 112315-1–112315-6. doi:10.1016/j.fusengdes.2021.112315
info:cnr-pdr/source/autori:De Angeli M.; Ripamonti D.; Ghezzi F.; Tolias P.; Conti C.; Arnas C.; Jerab M.; Rudakov D.L.; Chrobak C.P.; Irby J.; LaBombard B.; Lipschultz B.; Maddaluno G./titolo:Cross machine investigation of magnetic tokamak dust: Morphological and elemental analysis/doi:10.1016%2Fj.fusengdes.2021.112315/rivista:Fusion engineering and design/anno:2021/pagina_da:112315-1/pagina_a:112315-6/intervallo_pagine:112315-1–112315-6/volume:166
International audience; The presence of magnetic dust can be an important issue for future fusion reactors where plasma breakdown is critical. Magnetic dust has been collected from contemporary fusion devices (FTU, Alcator C-Mod, COMPASS and DIII-D)
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a36d5f29e8eb3c0052f5da6a4a960b00
http://hdl.handle.net/20.500.12278/34203
http://hdl.handle.net/20.500.12278/34203