Zobrazeno 1 - 10
of 440
pro vyhledávání: '"T Loarer"'
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:
Y. Kovtun, T. Wauters, D. Matveev, R. Bisson, I. Jepu, S. Brezinsek, I. Coffey, E. Delabie, A. Boboc, T. Dittmar, A. Hakola, P. Jacquet, K. Kirov, E. Lerche, J. Likonen, E. Litherland-Smith, T. Loarer, P. Lomas, C. Lowry, E. Pawelec, C. Perez von Thun, A. Meigs, M. Maslov, I. Monakhov, C. Noble, S. Silburn, H. Sun, D. Taylor, E. Tsitrone, A. Widdowson, H. Sheikh, D. Douai
Publikováno v:
Nuclear Materials and Energy, Vol 37, Iss , Pp 101521- (2023)
This paper explores the plasma parameters of helium and hydrogen Ion Cyclotron Wall Conditioning (ICWC) discharges performed in JET as part of a He/H fuelling changeover experiment. The conducted study shows that plasma with a higher density is forme
Externí odkaz:
https://doaj.org/article/8b41282043384df6ba22fdc43ab8859c
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:
J. Gaspar, F. Rigollet, N. Ehret, Y. Anquetin, E. Bernard, Y. Corre, M. Diez, M. Firdaouss, M. Houry, T. Loarer, C. Martin, M. Missirlian, P. Moreau, C. Pocheau, P. Reihlac, M. Richou, E. Tsitrone
Publikováno v:
Nuclear Materials and Energy, Vol 33, Iss , Pp 101305- (2022)
This paper summarizes the emissivity measurements performed on the shaped ITER-like plasma facing units (PFU) of the WEST lower divertor installed for the second phase of WEST. Laboratory measurements before their installation in WEST, as well as mea
Externí odkaz:
https://doaj.org/article/d3a96de063394f2386e28e63afac5781
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
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
Autor:
M-H. Aumeunier, J. Gerardin, C. Talatizi, M. Le Bohec, M. Ben Yaala, L. Marot, T. Loarer, R. Mitteau, J. Gaspar, F. Rigollet, X. Courtois, M. Houry, A. Herrmann, M. Faitsch
Publikováno v:
Nuclear Materials and Energy, Vol 26, Iss , Pp 100879- (2021)
Infra-red (IR) thermography is a widely used tool in fusion devices to monitor and to protect the plasma-facing component (PFC) from excessive heat loads. However, with the use of all-metal walls in fusion devices, deriving surface temperature from I
Externí odkaz:
https://doaj.org/article/6d043e02bd81448ab3cb9ed0edeef0e4