CNR ExploRA

Abstract in atti di convegno, 2018, ENG

SOL Transport and Filamentary Dynamics in High Density Tokamak Regimes

Vianello N.; D. Carralero; C. K. Tsui; V. Naulin; M. Agostini; J. Boedo; B. Labit; C. Theiler; D. Aguiam; S. Allan; M. Bernert; S. Costea; I. Cziegler; H. De Oliveira; J. Galdon-Quiroga; G. Grenfell; A. Hakola; C. Ionita; H. Isliker; A. Karpushov; J. Kovacic; B. Lipschultz; R. Maurizio; K. McClements; F. Militello; J. Olsen; J.J. Rasmussen; T. Ravensbergen; H. Reimerdes; B. Schneider; R. Schrittwieser; M. Spolaore; K. Verhaegh; J. Vicente; N. Walkden; W. Zhang; E. Wolfrum; the ASDEX-Upgrade Team; the TCV team; the EUROfusion MST1 Team

1 Consorzio RFX (CNR, ENEA, INFN, Università di Padova, Acciaierie Venete SpA), Corso Stati Uniti 4 - 35127 Padova, Italy; 2 Max-Planck-Institut für Plasmaphysik, Garching, Germany; 3 CIEMAT Laboratorio Nacional de Fusión, Madrid, Spain; 4 EPFL-SPC, Switzerland; 5 UCSD, La Jolla, USA; 6 DTU, Copenhagen, Denmark; 7 IPFN, Instituto Superior Técnico, Lisboa, Portugal; 8 CCFE, Culham, UK; 9 Institute for Ion Physics and Applied Physics, Innsbruck, Austria; 10 York Plasma Institute, University of York, UK; 11 University of Seville, Seville Spain; 12 VTT, Espoo, Finland; 13 Aristotle University of Thessaloniki, Greece; 14 Jozef Stefan Institute, Ljubljana; 15 FOM Institute DIFFER, Association EURATOM-FOM, Nieuwegein, Netherlands; 16 DIFFER--Dutch Institute for Fundamental Energy Research, Netherlands; 17 See the author list S. Coda et al 2017 Nucl. Fusion 57 102011; 18 See the author list H. Meyer et al 2017 Nucl. Fusion 57 102014 (N. Vianello1, D. Carralero2, 3, C. K. Tsui4, 5, V. Naulin6, M. Agostini1, J. Boedo4, B. Labit5, C. Theiler5, D. Aguiam7, S. Allan8, M. Bernert3, S. Costea9, I. Cziegler10, H. De Oliveira5, J. Galdon-Quiroga11, G. Grenfell1, A. Hakola12, C. Ionita9, H. Isliker13, A. Karpushov5, J. Kovacic14, B. Lipschultz10, R. Maurizio4, K. McClements8, F. Militello8, J. Olsen6, J. J. Rasmussen6, T. Ravensbergen16, H. Reimerdes5, B. Schneider9, R. Schrittwieser9, M. Spolaore1, K. Verhaegh10, J. Vicente7, N. Walkden8, W. Zhang3, E. Wolfrum3, the ASDEX-Upgrade Team2, the TCV team17 and and the EUROfusion MST1 Team18)

Addressing the role of scrape off layer filamentary transport is a subject of intense studies in fusion science. Intermittent structures dominate transport in L-Mode and strongly contribute to particle and energy losses in H-mode. The role of convective radial losses has become even more important due to its contribution to the shoulder formation in L-Mode, describing the progressive flattening of the density scrape off layer profile at high density r1- 3s. Investigation of this process revealed the strong relationship between divertor conditions and the upstream profiles, mediated by filaments dynamics which varies according to the downstream conditions. Preliminary investigations suggested that similar mechanisms occur in H-Mode r1s and that filaments contribute the SOL transport in H-mode density limit (HDL) as well r4s. The present contribution will report on results obtained on ASDEXUpgrade and TCV tokamaks, to address the role of filamentary transport in high density regimes both in L- and H-Mode. The combined results enlarge the operational space, from a device with a closed divertor, metallic first wall and cryogenic pumping system to a carbon machine with a completely open divertor. The mechanism of shoulder formation and the role of filaments have been tested against variation of plasma current, magnetic configuration (single and double null plasmas), and divertor neutral densities, through modification of cryopump efficiency. At constant magnetic field the density decay length increases with filament-size independently of the plasma current for both machines in L-mode, consistently with the fact that upstream profiles and divertor neutral pressure exhibit the same trend with normalized Greenwald fraction.

27th IAEA Fusion Energy Conference (FEC 2018), pp. 396–396, Ahmedabad, India, 22-27 October 2018