G P Maddison A E Hubbard J W Hughes J A Snipes B Labombard I M Nunes M N A Beurskens S K Erents M A H Kempenaars B Alper S D Pinches M Valovic R Pasqualotto A Alfier E Giovannozzi JET EFDA Contributors
Experiments on the Alcator C-Mod and JET tokamaks with identical values of nondimensional variables at the pedestal top are expected to have the same local plasma transport for a ratio > 4 in absolute size and thus can help to clarify other effects in pedestal formation. At the high and low fields (7.9 T, 1.4 T respectively) involved, natural-densi…
PublishedH Meyer R J Akers F Alladio L C Appel K B Axon N Ben Ayed P Boerner R J Buttery P G Carolan D Ciric C D Challis I T Chapman Et Al
Several improvements to the MAST plant and diagnostics have facilitated new studies advancing the physics basis for ITER and DEMO, as well as for future spherical tokamaks. Using the increased heating capabilities PNBI ≤ 3.8 MWH-mode at Ip = 1.2 MA was accessed showing that the energy confinement on MAST scales more weakly with Ip and more strong…
PublishedE.S. Marmar A. Bader M. Bakhtiari H. Barnard W. Beck I. Bespamyatnov A. Binus P. Bonoli B. Bose M. Bitter I. Cziegler G. Dekow et al.
This paper summarizes highlights of research results from the Alcator C-Mod tokamak covering the period 2006 through 2008. Active flow drive, using mode converted waves in the ion cyclotron range of frequencies (ICRF), has been observed for the first time in a tokamak plasma, using a mix of D and 3 He ion species; toroidal and poloidal flows are dr…
PublishedM. Bécoulet G. Huysmans X. Garbet E. Nardon D. Howell A.Garofalo M. Schaffer T. Evans K. Shaing A. Cole J.-K. Park P. Cahyna
Non-linear reduced MHD modelling of the response of a toroidally rotating plasma on Resonant Magnetic Perturbations (RMPs) is presented for DIII-D and ITER typical parameter. The non-linear cylindrical reduced MHD (RMHD) code was adapted to take into account toroidal rotation and plasma braking mechanisms such as resonant braking (~jxB) and the Neo…
PublishedF. Militello F.L. Waelbroeck
The penetration of the magnetic field in a rotating inhomogeneous plasma is investigated with direct numerical simulations. The main focus of this work is to test the linear, singular-layer models when diamagnetic and finite Larmor radius effects are included. Our results confirm the existing analytical prediction when the plasma velocity at the re…
PublishedM. Turnyanskiy D. L. Keeling R. J. Akers G. Cunningham N. J. Conway H. Meyer C. A. Michael S. D. Pinches
One of the main operational aims of the MAST experiment [1] and the proposed MAST upgrade is to investigate possible mechanisms to control the q-profile and drive off-axis current. Experiments were carried out to determine the extent to which the q-profile may be modified using two different approaches, transient and steady-state. Transient effects…
PublishedJ.G. Cordey
Recently several tokamak experiments have been completed to try and elucidate the scaling of the confinement with the key dimensionless parameters ρ*, ν* and β. It has been shown theoretically that these 3 parameters are fundamental in determining the scaling of the energy confinement [1-3]. The experimental results, which consist of single scan…
PublishedJ. W. Connor A. Fasoli C. Hidalgo A. Kirk V. Naulin A. G. Peeters T. Tala
This workshop on transport in fusion plasmas is the thirteenth in a series. Previously they have been held under the auspices of the EU and US Transport Task Forces (TTFs), with J Connor as the EU TTF chair. However, the EU Transport Task Force has now been subsumed into the EFDA (European Fusion Development Agreement) Topical Group for Transport (…
PublishedG. De Temmerman R.P. Doerner
The prediction of tritium retention in ITER relies on the extrapolation from present data. An empirical equation was proposed in (De Temmerman G. et al 2008 Nucl. Fusion 48 075008) to account for the influence of the beryllium deposition rate, the substrate temperature and the average energy of the deuterium neutrals on the deuterium retention. How…
Published