Transport effects of low (m,n) MHD modes on TFTR supershots

Supershots in TFTR often suffer a performance deterioration characterized by a gradual decrease of the DD fusion neutron yield and plasma stored energy after several hundred milliseconds of auxiliary heating. The correlation between this performance deterioration and the development of low m (the poloidal mode number), n (the toroidal mode number) MHD modes is studied through shot-to-shot comparisons and statistical data analyses. A good correlation is observed between performance deterioration and the appearance of strong 3/2 and 4/3 macroscopic modes. The magnetic island structures are observed using Mirnov and ECE diagnostics. The measured Te, Ti and ne profiles show that development of the islands corresponds to a nearly constant decrement of these quantities over the core region r τE). The observed energy deterioration scaling, δW/W varies as w/a, where w is the magnetic island width and a is the plasma minor radius, agrees with a local transport model. Numerical simulations based on the local transport model reveal many features consistent with the experiments. Besides the MHD effect, it is found that a continuous increase of edge recycling rate during the neutral beam injection phase also has a large effect on the performance deterioration

[1]  Harold P. Furth,et al.  Finite‐Resistivity Instabilities of a Sheet Pinch , 1963 .

[2]  G. H. Miley,et al.  Fusion cross sections and reactivities , 1974 .

[3]  B. V. Waddell,et al.  Saturation of the tearing mode , 1976 .

[4]  D. McCune,et al.  New techniques for calculating heat and particle source rates due to neutral beam injection in axisymmetric tokamaks , 1981 .

[5]  R. Grimm,et al.  Study of high-beta magnetohydrodynamic modes and fast-ion losses in PDX , 1983 .

[6]  R. Gruber,et al.  MHD-limits to plasma confinement , 1984 .

[7]  Robert James Goldston Energy confinement scaling in Tokamaks: some implications of recent experiments with Ohmic and strong auxiliary heating , 1984 .

[8]  R. Carrera,et al.  Island bootstrap current modification of the nonlinear dynamics of the tearing mode , 1986 .

[9]  N. Sauthoff,et al.  TFTR Mirnov loop system , 1986 .

[10]  J. Manickam,et al.  Ideal MHD stability properties of pressure driven modes in low shear tokamaks , 1987 .

[11]  Davis,et al.  High-temperature plasmas in a tokamak fusion test reactor. , 1987, Physical review letters.

[12]  Tadashi Sekiguchi,et al.  Plasma Physics and Controlled Nuclear Fusion Research , 1987 .

[13]  H. Park,et al.  Multichannel far-infrared laser interferometer for electron density measurements on the tokamak fusion test reactor. , 1987, Applied optics.

[14]  T. Hender,et al.  Finite beta effects on tearing modes in the tokamak , 1987 .

[15]  R. Rocco,et al.  Broadband measurement of electron cyclotron emission in TFTR using a quasioptical light collection system and a polarizing Michelson interferometer , 1988 .

[16]  K. Hattori,et al.  Determination of the structure of magnetic islands on TFTR (invited) , 1988 .

[17]  A. Cavallo,et al.  Twenty-channel grating polychromator for millimeter wave plasma emission measurements , 1988 .

[18]  Tx,et al.  From Particles to Plasmas , 1989 .

[19]  J. Snipes,et al.  Plasma stored energy and momentum losses during large MHD activity in JET , 1990 .

[20]  J. Callen,et al.  Global energy confinement degradation due to macroscopic phenomena in tokamaks , 1990 .

[21]  R. White,et al.  Mode–particle resonances during near‐tangential neutral beam injection in the Tokamak Fusion Test Reactor , 1990 .

[22]  A. T. Ramsey,et al.  Enhanced carbon influx into TFTR supershots , 1991 .

[23]  K. Thomsen,et al.  Fishbone activity in JET , 1991 .

[24]  Robert J. Goldston,et al.  Data analysis on TFTR using the SNAP transport code , 1992 .

[25]  H. Mynick,et al.  Anomalous delayed loss of trapped D-D fusion products in TFTR , 1993 .

[26]  N. Hosogane Confinement and divertor studies in Japan Tokamak JT‐60U* , 1993 .

[27]  E. Thompson,et al.  The use of neutral beam heating to produce high performance fusion plasmas, including the injection of tritium beams into the Joint European Torus (JET)* , 1993 .

[28]  R. Budny,et al.  Role of neutral-beam fuelling profile in energy confinement and neutron emission on TFTR , 1994 .

[29]  J. Stevens,et al.  ICRF heating of TFTR deuterium supershot plasmas in the 3He minority regime , 1994 .

[30]  J. Strachan Studies of global energy confinement in TFTR supershots , 1994 .