Zobrazeno 1 - 10
of 1 823
pro vyhledávání: '"Tamain P."'
Autor:
H. Bufferand, G. Ciraolo, R. Düll, G. Falchetto, N. Fedorczak, Y. Marandet, V. Quadri, M. Raghunathan, N. Rivals, F. Schwander, E. Serre, S. Sureshkumar, P. Tamain, N. Varadarajan
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101824- (2024)
First principle modelling of edge plasma turbulence including neutrals and plasma recycling on the wall remains a challenge, in particular due to the long time scales necessary to simulate to reach particle balance. In this contribution, we propose a
Externí odkaz:
https://doaj.org/article/af4a47461ece4cef88891bd5d5e5aef7
Autor:
N. Varadarajan, H. Bufferand, G. Ciraolo, L. Cappelli, P. Tamain, N. Rivals, S. Sureshkumar, V. Quadri, L. de Gianni
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101818- (2024)
The W impurity species was introduced in the multi-component edge fluid code SOLEDGE3X, in its 2D transport version. To do so, several physical ingredients have been implemented. Firstly, W gross erosion is calculated using the Garcia-Rosales formula
Externí odkaz:
https://doaj.org/article/cde4336e5c6e4c60892ee9c7fabe141f
Autor:
Raffael Düll, Guido Ciraolo, Hugo Bufferand, Eric Serre, Virginia Quadri, Nicolas Rivals, Patrick Tamain, Srikanth Sureshkumar, Naren Varadarajan
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101807- (2024)
The fluid-drift code SOLEDGE3X, developed by CEA/IRFM in collaboration with Aix-Marseille University, is a powerful tool for simulating transport and turbulence in tokamak edge plasmas with axisymmetric magnetic configurations. In tokamaks such as WE
Externí odkaz:
https://doaj.org/article/44639a998e6248bdbcc8d204c56659df
Autor:
S. Sureshkumar, N. Rivals, P. Tamain, X. Bonnin, R. Pitts, Y. Marandet, G. Ciraolo, H. Bufferand, G. Falchetto, N. Fedorczak, V. Quadri, M. Raghunathan, F. Schwander, E. Serre, R. Düll, N. Varadarajan
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101780- (2024)
Boundary plasma simulations are essential to estimate expected divertor and first wall (FW) heat and particle loads on ITER during burning plasma operation. A key missing feature of existing SOLPS simulations (Pitts et al., 2019) is the absence of a
Externí odkaz:
https://doaj.org/article/00c27ea3e4cf412fbbac8815ac604176
Autor:
M. Scotto d’Abusco, I. Kudashev, G. Giorgiani, A. Glasser-Medvedeva, F. Schwander, E. Serre, J. Bucalossi, H. Bufferand, G. Ciraolo, P. Tamain
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101750- (2024)
This work explores the Limiter–Divertor transition (L–D) during the current ramp-up of ITER’s Q = 10 baseline plasma scenario at various central line-integrated density nli values. The analysis, based on transport simulations performed with the
Externí odkaz:
https://doaj.org/article/9284628542dd46b9ab57a3ac23c4b0c3
Autor:
N. Rivals, N. Fedorczak, P. Tamain, H. Bufferand, G. Ciraolo, H. Yang, Y. Marandet, J. Gaspar, E. Geulin, J.P. Gunn, C. Guillemaut, J. Morales, P. Manas, R. Nouailletas, M. Dimitrova, J. Cavalier, J. Svoboda, H. Reimerdes, D. Brida, T. Lunt, M. Bernert
Publikováno v:
Nuclear Materials and Energy, Vol 40, Iss , Pp 101723- (2024)
X-Point Radiator (XPR) regimes have been obtained in WEST tokamak experiments with nitrogen seeding during the experimental campaigns of 2023 and 2024. These experiments showed the formation of a stable toroidal radiating ring near the X-point, simil
Externí odkaz:
https://doaj.org/article/2f16cc78d74b4b22a9273231a31fb284
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:
Bufferand, H., Ciraolo, G., Düll, R., Falchetto, G., Fedorczak, N., Marandet, Y., Quadri, V., Raghunathan, M., Rivals, N., Schwander, F., Serre, E., Sureshkumar, S., Tamain, P., Varadarajan, N.
Publikováno v:
In Nuclear Materials and Energy December 2024 41