Zobrazeno 1 - 10
of 1 465
pro vyhledávání: '"J. GASPAR"'
Autor:
J. Gerardin, Y. Corre, C. Desgranges, M. Diez, L. Dubus, M. Firdaouss, J. Gaspar, A. Grosjean, C. Guillemaut, C. Hernandez, A. Huart, H. Roche, S. Vives
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101783- (2024)
After 3 h of accumulated time from repeated plasma shots during C7 campaign performed in 2023, a deposited layer appeared on the ITER-grade W-monoblock of the lower divertor of WEST, mostly on the high field side. The growth of the deposit was observ
Externí odkaz:
https://doaj.org/article/1a182519497840239fbbaf4daade2212
Autor:
Y. Anquetin, J. Gaspar, Y. Corre, JL. Gardarein, J. Gerardin, P. Malard, F. Rigollet, Q. Tichit, E. Tsitrone
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101788- (2024)
The estimation of the heat flux density distribution profiles in tokamak devices is a very important research topic for edge plasma physics purposes and also to ensure the safety of the machine. In the radial direction, the heat flux exhibits an expo
Externí odkaz:
https://doaj.org/article/e259c1d3e6494c1e8677d24880016b56
Autor:
N. Fedorczak, C. Arnas, L. Cappelli, L. Colas, Y. Corre, M. Diez, A. Gallo, J. Gaspar, A. Grosjean, C. Guillemaut, J.P. Gunn, C. Johnson, C. Martin, E. Tsitrone, E.A. Unterberg, J. Bucalossi
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101758- (2024)
An initial high fluence campaign was performed in WEST, in 2023, on the newly installed actively cooled tungsten divertor composed of ITER-grade monoblocks. The campaign consisted in the repetition of a 60 s long Deuterium L-mode pulse in attached di
Externí odkaz:
https://doaj.org/article/76f629b6a2384a68ad47215f29438211
Autor:
C. Martin, M. Diez, E. Bernard, M. Cabié, A. Campos, C. Pardanaud, G. Giacometti, A. Gallo, J. Gaspar, Y. Corre, E.Tsitrone
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101764- (2024)
We analysed deposits collected on the lower divertor of WEST after the first high fluence campaign performed in 2023. Deposits were collected on the high field side (thick deposition area) of 2 ITER-grade plasma facing units (PFUs), located on differ
Externí odkaz:
https://doaj.org/article/b318bc3f1e224a7b80bddf5a4a1337f3
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:
T. Wauters, R. Bisson, E. Delabie, D. Douai, A. Gallo, J. Gaspar, I. Jepu, Y. Kovtun, E. Pawelec, D. Matveev, A. Meigs, S. Brezinsek, I. Coffey, T. Dittmar, N. Fedorczak, J. Gunn, A. Hakola, P. Jacquet, K. Kirov, E. Lerche, J. Likonen, E. Litherland-Smith, T. Loarer, P. Lomas, C. Lowry, M. Maslov, I. Monakhov, J. Morales, C. Noble, R. Nouailletas, B. Pégourié, C. Perez von Thun, R.A. Pitts, C. Reux, F. Rimini, H. Sheikh, S. Silburn, H. Sun, D. Taylor, E. Tsitrone, S. Vartanian, E. Wang, A. Widdowson
Publikováno v:
Nuclear Materials and Energy, Vol 38, Iss , Pp 101587- (2024)
The pre-fusion power operation (PFPO) phase of ITER, as described in the ITER research plan with Staged Approach,22 ITER Organization, “ITER Research Plan within the Staged Approach,” ITR-18–003, Aug. 2018. includes both hydrogen (H) and helium
Externí odkaz:
https://doaj.org/article/6152aca246de47dcbefb89a44096943a
Autor:
Y. Corre, M-H. Aumeunier, A. Durif, J. Gaspar, K. Krieger, T. Loewenhoff, M. Richou, S. Ratynskaia, Q. Tichit, Y. Anquetin, R. Dejarnac, M. Diez, L. Dubus, M. Firdaouss, J. Gerardin, A.. Grosjean, J.P. Gunn, T. Loarer, P. Maget, C. Martin, K. Paschalidis, E. Tsitrone, M. Wirtz
Publikováno v:
Nuclear Materials and Energy, Vol 37, Iss , Pp 101546- (2023)
Assessing the performance of the ITER design for the tungsten (W) divertor Plasma Facing Units (PFUs) in a tokamak environment is a high priority issue to ensure efficient plasma operation. This paper reviews the most recent results derived from expe
Externí odkaz:
https://doaj.org/article/8daa185bfc6d47299e72398796f748a1
Autor:
Q. Tichit, A. Durif, J. Gaspar, Y. Anquetin, Y. Corre, M. Diez, L. Dubus, M. Firdaouss, J. Gerardin, A. Grosjean, J.P. Gunn, K. Krieger, M. Missirlian, S. Ratynskaia, P. Reilhac, M. Richou, F. Rigollet
Publikováno v:
Nuclear Materials and Energy, Vol 37, Iss , Pp 101537- (2023)
The consequences of tungsten (W) damaging processes, such as cracking and melting, on divertor lifetime and plasma operation are high priority issues for ITER. A sustained melting experiment was conducted in WEST using a 2 mm deep groove geometry on
Externí odkaz:
https://doaj.org/article/fd7599b33eb0402fbd322d8ecb4ff549
Autor:
M. Houry, M-H. Aumeunier, Y. Corre, X. Courtois, R. Mitteau, TH. Loarer, L. Dubus, E. Gauthier, J. Gerardin, V. Gorse, E. Grelier, A. Juven, PH. Malard, V. Moncada, Q. Tichit, S. Vives, J. Gaspar, the WEST Team
Publikováno v:
Nuclear Fusion, Vol 65, Iss 1, p 016059 (2024)
The protection of the inner walls of magnetic confinement fusion research reactors is a crucial issue, particularly in this research context where plasma scenarios are explored to reach high power performance, thus leading to high temperature of the
Externí odkaz:
https://doaj.org/article/3942316cd65a46c4bba524a62a96370e