F. Orain M. Bécoulet G. Dif-Pradalier G. Huijsmans S. Pamela E. Nardon C. Passeron G. Latu V. Grandgirard A. Fil A. Ratnani I. Chapman A. Kirk A. Thornton M. Hoelzl P. Cahyna
The interaction of static Resonant Magnetic Perturbations (RMPs) with the plasma flows is modeled in toroidal geometry, using the non-linear resistive MHD code JOREK, which includes the X-point and the scrape-off-layer. Two-fluid diamagnetic effects, the neoclassical poloidal friction and a source of toroidal rotation are introduced in the model to…
PublishedM. R. Gilbert P. Schuck B. Sadigh J. Marian
In body-centered-cubic (bcc) crystals, 1/2{111} screw dislocations exhibit high intrinsic lattice friction as a consequence of their nonplanar core structure, which results in a periodic energy landscape known as the Peierls potential UP. The main features determining plastic flow, including its stress and temperature dependences, can be derived di…
PublishedI. T. Chapman A. Kirk C. J. Ham J. R. Harrison Y. Q. Liu et al.
Type-I Edge Localised Modes (ELMs) have been mitigated in MAST through the application of n = 3, 4, and 6 resonant magnetic perturbations. For each toroidal mode number of the non-axisymmetric applied fields, the frequency of the ELMs has been increased significantly, and the peak heat flux on the divertor plates reduced commensurately. This increa…
PublishedF. Militello W. Fundamenski V. Naulin A.H. Nielsen
Numerical simulations of L-mode plasma turbulence in the Scrape Off Layer of MAST are presented. Relevant features of the boundary plasma, such as the thickness of the density layer or the statistics of the fluctuations are related to the edge density and temperature, plasma current and parallel connection length. It is found that the density profi…
PublishedF. Militello P. Tamain W. Fundamenski A. Kirk V. Naulin A.H. Nielsen The Mast Team
Numerical simulations of interchange turbulence in the Scrape-Off Layer are performed in a regime relevant for a specific L-mode MAST (Mega Ampere Spherical Tokamak) discharge. Such a discharge was diagnosed with a reciprocating arm equipped with a Gundestrup probe. A detailed comparison of the average and statistical properties of the simulated an…
PublishedO Crofts P Allan J Raimbach A Tesini C-H Choi C Damiani M Van Uffelen
The maintenance requirements for the equipment in the ITER Neutral Beam Cell requires components to be lifted and transported within the cell by remote means. To meet this requirement, the provision of an overhead crane with remote handling capabilities has been initiated. The layout of the cell has driven the design to consist of a monorail crane …
PublishedM. Maslov M.N.A. Beurskens M. Kempenaars J. Flanagan
The LIDAR Thomson scattering concept was proposed in 1983 and then implemented for the first time on the JET tokamak in 1987. A number of modifications were performed and published in 1995, but since then no major changes were made for almost 15 years. In 2010 a refurbishment of the diagnostic was started, with as main goals to improve its performa…
PublishedA. Stanier P. Browning M. Gordovskyy K. G. McClements M. P. Gryaznevich V. S. Lukin
In the merging-compression method of plasma start-up, two flux-ropes with parallel toroidal current are formed around in-vessel poloidal field coils, before merging to form a spherical tokamak plasma. This start-up method, used in the Mega-Ampere Spherical Tokamak (MAST), is studied as a high Lundquist number and low plasma-beta magnetic reconnecti…
PublishedJ. E. Rice Y. A. Podpaly M. L. Reinke R. Mumgaard S. D. Scott S. Shiraiwa G. M. Wallace B. Chouli C. Fenzi-Bonizec M. F. F. Nave P. H. Diamond C. Gao R. S. Granetz J.W. Hughes R. R. Parker Et Al
Application of lower hybrid (LH) current drive in tokamak plasmas can induce both co- and countercurrent directed changes in toroidal rotation, depending on the core q profile. For discharges with q0 < 1, rotation increments in the countercurrent direction are observed. If the LH-driven current is sufficient to suppress sawteeth and increase q0 abo…
PublishedR. Neu G. Arnoux M. Beurskens V. Bobkov S. Brezinsek et al.
To consolidate International Thermonuclear Experimental Reactor (ITER) design choices and prepare for its operation, Joint European Torus (JET) has implemented ITER’s plasma facing materials, namely, Be for the main wall and W in the divertor. In addition, protection systems, diagnostics, and the vertical stability control were upgraded and the h…
Published