Zobrazeno 1 - 10
of 318
pro vyhledávání: '"N Fedorczak"'
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:
L. Cappelli, J. Guterl, N. Fedorczak, D.L. Rudakov, G. Sinclair, T. Abrams, S. Di Genova, U. Losada, I. Bykov, Ž. Popović, D. Truong, J. Watkins, R.S. Wilcox, W.R. Wampler, E. Serre
Publikováno v:
Nuclear Materials and Energy, Vol 37, Iss , Pp 101551- (2023)
An experiment was performed in the DIII-D lower divertor to validate numerical SOL tungsten (W) impurity erosion and redeposition simulations against experimental data. The net and gross erosion of W were calculated as a function of the voltage (or b
Externí odkaz:
https://doaj.org/article/79819ce9f4b44d9888186355d009b6cf
Autor:
A. Grosjean, D.C. Donovan, C.A. Johnson, J.P. Gunn, C. Guillemaut, N. Fedorczak, C.C. Klepper, E.A. Unterberg
Publikováno v:
Nuclear Materials and Energy, Vol 35, Iss , Pp 101385- (2023)
WEST is an actively cooled, long-pulse tokamak with nearly all plasma-facing components (PFC) made of tungsten (W). One of the aims of WEST is to study plasma operation with W PFCs in preparation for long-pulse operation on W divertor devices like IT
Externí odkaz:
https://doaj.org/article/ea7ffa537f424792b4b878dad1797679
Autor:
M. Diez, M. Balden, S. Brezinsek, Y. Corre, N. Fedorczak, M. Firdaouss, E. Fortuna, J. Gaspar, J.P. Gunn, A. Hakola, T. Loarer, C. Martin, M. Mayer, P. Reilhac, M. Richou, E. Tsitrone, T. Vuoriheimo
Publikováno v:
Nuclear Materials and Energy, Vol 34, Iss , Pp 101399- (2023)
Studying the ageing of tungsten monoblocks, their erosion and their fuel inventory is the priority of the WEST post-mortem analyses programme. Actively-cooled ITER-like plasma-facing units (PFUs) and special W-coated marker lower divertor tiles were
Externí odkaz:
https://doaj.org/article/4c267e31473b478b99b4950da7c3da23
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:
J.B. Maeker, J.H. Nichols, D.C. Donovan, A. Grosjean, J. Gunn, N. Fedorczak, C. Guillemaut, C.C. Klepper, E.A. Unterberg, D.C. Easley, WEST Team
Publikováno v:
Nuclear Materials and Energy, Vol 33, Iss , Pp 101309- (2022)
The plasma background and impurity transport in the scrape-off layer (SOL) of the WEST tokamak are modeled for three discharges over a Psep power scan ranging between 1.5 and 2.35 MW. An extended modeling grid is used to investigate far-SOL sourcing
Externí odkaz:
https://doaj.org/article/ac8fdf16cfd340ea8f1dc2f1ed6477ac
Autor:
J.P. Gunn, J. Bucalossi, Y. Corre, M. Diez, E. Delmas, N. Fedorczak, A. Grosjean, M. Firdaouss, J. Gaspar, T. Loarer, M. Missirlian, P. Moreau, E. Nardon, C. Reux, M. Richou, E. Tsitrone
Publikováno v:
Nuclear Materials and Energy, Vol 27, Iss , Pp 100920- (2021)
In the WEST tokamak, ITER-like divertor targets consisting of tungsten monoblocks bonded via an OHFC-Cu compliance layer to CuCrZr cooling tubes were exposed to plasma during the 2018 experimental campaign in which modest heating power was available.
Externí odkaz:
https://doaj.org/article/cb69393d7d584860ae442e9a9945c8ce
Autor:
N. Fedorczak, J. Gaspar, Y. Corre, A. Grosjean, X. Courtois, J.P. Gunn, R. Mitteau, R. Dejarnac, J. Bucalossi, E. Tsitrone, T. Loarer, S. Brezinsek
Publikováno v:
Nuclear Materials and Energy, Vol 27, Iss , Pp 100961- (2021)
WEST is a full metallic tokamak with an extensive set of diagnostics for heat load measurements. In this paper, heat loads on the lower divertor of WEST are investigated using two independent methods. A first method relies on the thermal inversion of
Externí odkaz:
https://doaj.org/article/2ce9b9afccec426d88ee768fda7641d3