Numerical study of divertor detachment in TCV H-mode scenarios

被引:3
作者
Yang, H. [1 ]
Ciraolo, G. [1 ]
Fevrier, O. [2 ]
Galassi, D. [2 ]
Bucalossi, J. [1 ]
Bufferand, H. [1 ]
Gorno, S. [2 ]
Henderson, S. [3 ]
Reimerdes, H. [2 ]
Theiler, C. [2 ]
Bagnato, F. [2 ]
Falchetto, G. [1 ]
Fedorczak, N. [1 ]
Rivals, N. [1 ]
Tamain, P. [1 ]
机构
[1] CEA, IRFM, F-13108 St Paul Les Durance, France
[2] Ecole Polytech Fed Lausanne EPFL, Swiss Plasma Ctr SPC, Lausanne, Switzerland
[3] United Kingdom Atom Energy Author, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
关键词
plasma physics; H-mode; numerical modelling; divertor closure; nitrogen seeding; detachment; SCRAPE-OFF-LAYER; ASDEX UPGRADE; PLASMA DETACHMENT; DIII-D; TRANSPORT; TOKAMAK; WIDTH; EDGE; JET; SOL;
D O I
10.1088/1361-6587/ad06c7
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
The effect of divertor closure and nitrogen seeding on the detachment process has been studied by performing 2D numerical simulations of tokamak a configuration variable (TCV) H-mode divertor scenarios with the SOLEDGE3X-EIRENE edge plasma transport code. The simulations reveal that, in the cases with only deuterium gas fuelling, detachment occurs at a similar level of divertor neutral pressure ( approximate to 0.76 Pa), despite the difference in divertor closure achieved by changing the length of the outer baffle. Nitrogen reduces the target temperature with little effect on the upstream density and momentum loss but drops the upstream pressure, leading to a decrease in the target particle flux and divertor neutral pressure. Furthermore, when the radiation front starts to move up from the outer target, the peak parallel heat flux level at the outer target remains approximately the same ( approximate to 2.3 MW m-2), regardless of whether it is a deuterium fuelling scan, a nitrogen seeding scan at a fixed fuelling rate, or a change in the length of the outer baffle. An empirical partial detachment qualifier calibrated on AUG experimental data was compared with the TCV simulations. The results show good agreement in detachment state prediction, indicating the potential of this detachment qualifier to be applied in devices of different sizes, emphasizing the combined influence of input power entering the divertor, neutral pressure, and the concentration and species of impurity in achieving divertor detachment.
引用
收藏
页数:18
相关论文
共 69 条
  • [1] Heat and particle transport of SOL and divertor plasmas in the W shaped divertor on JT-60U
    Asakura, N
    Sakurai, S
    Hosogane, N
    Shimada, M
    Itami, K
    Koide, Y
    Naito, O
    [J]. NUCLEAR FUSION, 1999, 39 (11Y) : 1983 - 1994
  • [2] X-point radiation, its control and an ELM suppressed radiating regime at the ASDEX Upgrade tokamak
    Bernert, M.
    Janky, F.
    Sieglin, B.
    Kallenbach, A.
    Lipschultz, B.
    Reimold, F.
    Wischmeier, M.
    Cavedon, M.
    David, P.
    Dunne, M. G.
    Griener, M.
    Kudlacek, O.
    McDermott, R. M.
    Treutterer, W.
    Wolfrum, E.
    Brida, D.
    Fevrier, O.
    Henderson, S.
    Komm, M.
    [J]. NUCLEAR FUSION, 2021, 61 (02)
  • [3] Power exhaust by SOL and pedestal radiation at ASDEX Upgrade and JET
    Bernert, M.
    Wischmeier, M.
    Huber, A.
    Reimold, F.
    Lipschultz, B.
    Lowry, C.
    Brezinsek, S.
    Dux, R.
    Eich, T.
    Kallenbach, A.
    Lebschy, A.
    Maggi, C.
    McDermott, R.
    Puetterich, T.
    Wiesen, S.
    [J]. NUCLEAR MATERIALS AND ENERGY, 2017, 12 : 111 - 118
  • [4] Three-dimensional modelling of edge multi-component plasma taking into account realistic wall geometry
    Bufferand, H.
    Tamain, P.
    Baschetti, S.
    Bucalossi, J.
    Ciraolo, G.
    Fedorczak, N.
    Ghendrih, Ph
    Nespoli, F.
    Schwander, F.
    Serre, E.
    Marandet, Y.
    [J]. NUCLEAR MATERIALS AND ENERGY, 2019, 18 : 82 - 86
  • [5] Numerical modelling for divertor design of the WEST device with a focus on plasma-wall interactions
    Bufferand, H.
    Ciraolo, G.
    Marandet, Y.
    Bucalossi, J.
    Ghendrih, Ph.
    Gunn, J.
    Mellet, N.
    Tamain, P.
    Leybros, R.
    Fedorczak, N.
    Schwander, F.
    Serre, E.
    [J]. NUCLEAR FUSION, 2015, 55 (05)
  • [6] Impurity leakage and radiative cooling in the first nitrogen and neon seeding study in the closed DIII-D SAS configuration
    Casali, L.
    Eldon, D.
    McLean, A.
    Osborne, T.
    Leonard, A.
    Grierson, B.
    Ren, J.
    [J]. NUCLEAR FUSION, 2022, 62 (02)
  • [7] Neutral leakage, power dissipation and pedestal fueling in open vs closed divertors
    Casali, L.
    Eldon, D.
    Boedo, J. A.
    Leonard, T.
    Covele, B.
    [J]. NUCLEAR FUSION, 2020, 60 (07)
  • [8] The effect of neutrals in the new SAS divertor at DIII-D as modelled by SOLPS
    Casali, L.
    Covele, B. M.
    Guo, H. Y.
    [J]. NUCLEAR MATERIALS AND ENERGY, 2019, 19 : 537 - 543
  • [9] Modelling the effect of divertor closure on detachment onset in DIII-D with the SOLPS code
    Casali, L.
    Sang, C.
    Moser, A. L.
    Covele, B. M.
    Guo, H. Y.
    Samuell, C.
    [J]. CONTRIBUTIONS TO PLASMA PHYSICS, 2018, 58 (6-8) : 725 - 731
  • [10] SOLPS modelling of ASDEX upgrade H-mode plasma
    Chankin, A. V.
    Coster, D. P.
    Dux, R.
    Fuchs, Ch
    Haas, G.
    Herrmann, A.
    D Horton, L.
    Kallenbach, A.
    Kaufmann, M.
    Konz, Ch
    Lackner, K.
    Maggi, C.
    Mueller, H. W.
    Neuhauser, J.
    Pugno, R.
    Reich, M.
    Schneider, W.
    [J]. PLASMA PHYSICS AND CONTROLLED FUSION, 2006, 48 (06) : 839 - 868