Zobrazeno 1 - 10
of 301
pro vyhledávání: '"H Bufferand"'
Autor:
K. Afonin, A. Gallo, R. Lunsford, S. Bose, Y. Marandet, P. Moreau, G. Bodner, H. Bufferand, G. Ciraolo, C. Desgranges, P. Devynck, A. Diallo, J. Gaspar, C. Guillemaut, R. Guirlet, J.P. Gunn, N. Fedorczak, Y. Corre, F. Nespoli, N. Rivals, T. Loarer, P. Tamain, E.A. Unterberg
Publikováno v:
Nuclear Materials and Energy, Vol 40, Iss , Pp 101724- (2024)
Reactor relevant fusion devices will use tungsten (W) for their plasma facing components (PFCs) due to its thermomechanical properties and low tritium retention. However, W introduces high-Z impurities into the plasma, degrading its performance. Diff
Externí odkaz:
https://doaj.org/article/7103fdfb5d964d69b597b912904f8907
Autor:
I. Kudashev, M. Scotto d’Abusco, A. Glasser, E. Serre, F. Schwander, H. Bufferand, G. Ciraolo, P. Ghendrih, P. Tamain
Publikováno v:
Frontiers in Physics, Vol 12 (2024)
This paper deals with the distribution of sources, transport, and exhaust of particles in a tokamak. Knowledge and understanding of all the physical phenomena involved in the global particle buildup are necessary to study and predict density regimes
Externí odkaz:
https://doaj.org/article/87ec37f5ebbe4ab688c83093506fcea0
Autor:
L. De Gianni, G. Ciraolo, G. Giruzzi, G. Falchetto, N. Rivals, K. Gałązka, L. Balbinot, N. Varadarajan, S. Sureshkumar, J. F. Artaud, H. Bufferand, R. Düll, A. Gallo, P. Ghendrih, V. Quadri, G. Rubino, P. Tamain
Publikováno v:
Frontiers in Physics, Vol 12 (2024)
In its first phase of exploitation, JT-60SA will be equipped with an inertially cooled divertor, which can sustain heat loads of 10 MW/m2 on the targets for a few seconds, which is much shorter than the intended discharge duration. Therefore, in orde
Externí odkaz:
https://doaj.org/article/f6078db6883d42d48a6f5b1537c5c825
Autor:
S. Di Genova, G. Ciraolo, A. Gallo, J. Romazanov, N. Fedorczak, H. Bufferand, P. Tamain, N. Rivals, Y. Marandet, S. Brezinsek, E. Serre
Publikováno v:
Nuclear Materials and Energy, Vol 34, Iss , Pp 101340- (2023)
Numerical analysis is a useful tool to investigate tungsten (W) sources and transport across plasma in W Environment Steady state Tokamak (WEST) plasma discharges, as it highlights physical mechanisms not always directly observable in experiments. Mo
Externí odkaz:
https://doaj.org/article/19c8fa4db8ca4d23af91743f5a679d9e
Autor:
H. Yang, G. Ciraolo, J. Bucalossi, H. Bufferand, N. Fedorczak, P. Tamain, G. Falchetto, N. Rivals, J.P. Gunn, Y. Marandet, B. Pégourié, S. Vartanian
Publikováno v:
Nuclear Materials and Energy, Vol 33, Iss , Pp 101302- (2022)
In WEST experimental campaign C5, the divertor pumping capability has been improved by sealing the space between the divertor outer baffle and the vacuum vessel. It is expected that the degree of baffle leakage influences the transport of neutral par
Externí odkaz:
https://doaj.org/article/a981e0b26c014a99b738703c42d57d99
Autor:
P. Tamain, H. Bufferand, G. Ciraolo, C. Giroud, Y. Marandet, F. Militello, D. Moulton, N. Vianello
Publikováno v:
Nuclear Materials and Energy, Vol 27, Iss , Pp 100989- (2021)
The modelling of JET corner configurations, in which the strike points are positioned deep in the corners of the divertor, is extremely challenging for edge plasma fluid modelling tools. To circumvent this technical limitation, a geometrical approxim
Externí odkaz:
https://doaj.org/article/2dfa9956847a4869ab00983f2cd74fbf
Publikováno v:
Nuclear Materials and Energy, Vol 27, Iss , Pp 100985- (2021)
On the way to the development of a fusion reactor based on the Tokamak configuration, the Divertor Test Tokamak facility (DTT) [1] in construction in Italy should provide useful information for the DEMO [2] reactor in the field of the power and parti
Externí odkaz:
https://doaj.org/article/17b8b98a38124e6da5f9a4c460597eb1
Publikováno v:
Nuclear Materials and Energy, Vol 19, Iss , Pp 433-439 (2019)
Radial transport in scrape off layer is commonly attributed to the intermittent convection of plasma filaments. These filaments are observed in experiments, and commonly reproduced by turbulent simulations. These simulations are able to reproduce bot
Externí odkaz:
https://doaj.org/article/4fbf09d3295d4b37b6301f46409a0e51
Autor:
J. Denis, J. Bucalossi, G. Ciraolo, E.A. Hodille, B. Pégourié, H. Bufferand, C. Grisolia, T. Loarer, Y. Marandet, E. Serre
Publikováno v:
Nuclear Materials and Energy, Vol 19, Iss , Pp 550-557 (2019)
An extension of the SolEdge2D-EIRENE code package, named D-WEE, has been developed to add the dynamics of thermal desorption of hydrogen isotopes from the surface of plasma facing materials. To achieve this purpose, D-WEE models hydrogen isotopes imp
Externí odkaz:
https://doaj.org/article/61e2f0347c32479bb50745d38d4113b0
Publikováno v:
Nuclear Materials and Energy, Vol 19, Iss , Pp 200-204 (2019)
A reduced model for radial anomalous transport of plasma in tokamaks, inspired by the Reynolds-Averaged Navier–Stokes (RANS) approach, is presented assuming diffusion as governing mechanism. In order to self-consistently calculate transport coeffic
Externí odkaz:
https://doaj.org/article/261864405f574b60b2258f6bf751c355