Zobrazeno 1 - 10
of 128
pro vyhledávání: '"S. Pestchanyi"'
Autor:
R.A. Pitts, S. Bardin, B. Bazylev, M.A. van den Berg, P. Bunting, S. Carpentier-Chouchana, J.W. Coenen, Y. Corre, R. Dejarnac, F. Escourbiac, J. Gaspar, J.P. Gunn, T. Hirai, S-H. Hong, J. Horacek, D. Iglesias, M. Komm, K. Krieger, C. Lasnier, G.F. Matthews, T.W. Morgan, S. Panayotis, S. Pestchanyi, A. Podolnik, R.E. Nygren, D.L. Rudakov, G. De Temmerman, P. Vondracek, J.G. Watkins
Publikováno v:
Nuclear Materials and Energy, Vol 12, Iss , Pp 60-74 (2017)
The key remaining physics design issue for the ITER tungsten (W) divertor is the question of monoblock (MB) front surface shaping in the high heat flux target areas of the actively cooled targets. Engineering tolerance specifications impose a challen
Externí odkaz:
https://doaj.org/article/37e9ff733873443b91055f6eac330a43
Publikováno v:
Nuclear Materials and Energy, Vol 12, Iss , Pp 959-966 (2017)
Disruption mitigation by massive gas injection (MGI) of Ne gas has been simulated using the 3D TOKES code that includes the injectors of the Disruption Mitigation System (DMS) as it will be implemented in ITER. The simulations have been done using a
Externí odkaz:
https://doaj.org/article/704d80be969d45a3aebb0cee524a5482
Publikováno v:
Nuclear Materials and Energy, Vol 9, Iss C, Pp 98-103 (2016)
Simulation of beryllium cracking under action of multiple severe surface heatings has been performed using the PEGASUS-3D code and verified by experiments in the JUDITH 1 facility. Analysis of the results has revealed beryllium thermo conductivity de
Externí odkaz:
https://doaj.org/article/b9eacb48e1f240d5b2cce69036bc4647
Akademický článek
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Autor:
Boris Bazylev, Panagiotis Tolias, S. Pestchanyi, R.A. Pitts, Svetlana V. Ratynskaia, E. Thoren, EUROfusion Mst Team, K. Krieger
Publikováno v:
Nuclear Materials and Energy, Vol 17, Iss, Pp 194-199 (2018)
Nuclear Materials and Energy
Nuclear Materials and Energy
The first MEMOS 3D simulations of liquid metal motion on an inclined bulk tungsten sample transiently molten by edge-localized modes (ELMs) are reported. The exposures took place at the outer ASDEX-Upgrade divertor with the tungsten surface tangent i
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::62061145e4a9c7bc77cdb446d01a9e06
http://www.sciencedirect.com/science/article/pii/S235217911830098X
http://www.sciencedirect.com/science/article/pii/S235217911830098X
Publikováno v:
Fusion Engineering and Design. 136:309-313
Fusion system codes are vital computational tools for the assessment of the key design parameters of a fusion power plant. The main goal is to capture the key physics and technology aspects, pushing the solution to comply with physics and engineering
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b6ebef4bbd1ba92381456549ed8cea4b
https://doi.org/10.1016/j.fusengdes.2018.02.014
https://doi.org/10.1016/j.fusengdes.2018.02.014
Autor:
Stanislav Herashchenko, Igor E. Garkusha, V.V. Chebotarev, Valery Valentynovych Staltsov, Nikolai V Kulik, Vadym A Makhlai, M.S. Ladygina, S. Pestchanyi, Yurij Petrov, Nikolai N Aksenov, O.V. Byrka
Publikováno v:
Nuclear Fusion. 61:116040
This paper presents experimental studies of plasma-surface interactions during powerful plasma impacts of a Quasi-Stationary Plasma Accelerator (QSPA) on the Sn capillary porous systems (CPSs) in conditions, simulating disruption and Edge Localized M
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::15675fad8d0ef85aa145b17f42776f14
https://doi.org/10.1088/1741-4326/ac26ec
https://doi.org/10.1088/1741-4326/ac26ec
Publikováno v:
Fusion Engineering and Design. 124:401-404
Measurements of tungsten (W) plasma shield dynamics have been performed in the 2MK-200 facility under ITER relevant disruptive plasma heat flux densities of ∼100 GW/m 2 . Plasma temperature profiles at two time instants and time dependent electron
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::de1c7ed63db96f82eb6944fc4e41a116
https://doi.org/10.1016/j.fusengdes.2017.02.048
https://doi.org/10.1016/j.fusengdes.2017.02.048
Autor:
P. Bunting, B. Bazylev, R. Dejarnac, T. Hirai, Richard E. Nygren, C.J. Lasnier, Yann Corre, D. Iglesias, M.A. van den Berg, R.A. Pitts, J. W. Coenen, S. Bardin, Petr Vondracek, Frederic Escourbiac, K. Krieger, James Paul Gunn, S. Panayotis, G. De Temmerman, S-H. Hong, S. Carpentier-Chouchana, Jonathan Gaspar, Dmitry Rudakov, J. Horacek, Matthias Komm, G. F. Matthews, S. Pestchanyi, A. Podolnik, Thomas Morgan, J.G. Watkins
Publikováno v:
Nuclear Materials and Energy, Vol 12, Iss, Pp 60-74 (2017)
Nuclear Materials and Energy
Nuclear materials and energy, 12, 60–74
Nuclear Materials and Energy, 12, 60-74
Nuclear Materials and Energy
Nuclear materials and energy, 12, 60–74
Nuclear Materials and Energy, 12, 60-74
The key remaining physics design issue for the ITER tungsten (W) divertor is the question of monoblock (MB) front surface shaping in the high heat flux target areas of the actively cooled targets. Engineering tolerance specifications impose a challen
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a47471332cd4433476352d22b5e5d837
http://www.sciencedirect.com/science/article/pii/S2352179116302885
http://www.sciencedirect.com/science/article/pii/S2352179116302885
Publikováno v:
Fusion Engineering and Design. 161:111976
TOKES simulations of mixed Ne/D2 pellet injection through 1 equatorial launcher into an ITER discharge of 280 MJ thermal plasma energy was carried out. Two kinds of pellets were simulated: ‘large’, containing 1.1∙1024 D2 molecules and ‘small
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::be9774789b4968c6490812a4f2ae9e65
https://doi.org/10.1016/j.fusengdes.2020.111976
https://doi.org/10.1016/j.fusengdes.2020.111976