Published June 2000 | Version v1
Journal article

Performance and control of optimized shear discharges in JET

  • 1. E-mail: alain.becoulet at cea.fr (France)
  • 2. Association Euratom - CEA sur la Fusion, CEA Cadarache, Saint-Paul-lez-Durance (France)
  • 3. JET Joint Undertaking, Abingdon, Oxfordshire (United Kingdom)

Description

High performance discharges are routinely obtained on JET with low or reversed magnetic shear (s = (r/q)dq/dr), and the potential for steady state operation of such discharges is under investigation. With the use of the proper heating and fuelling, these 'optimized shear' (OS) discharges exhibit an internal transport barrier (ITB), resulting in a strong peaking of the pressure profile, and thus in high fusion performance. These regimes have been extensively studied during the last (DD and DT) JET campaigns in order to promote this type of scenario as the basis for 'advanced tokamak' operation. A review is given of the highest performance achieved on JET OS discharges during the last experimental campaigns, in both DD (up to 5.6 x 1016 neutrons/s) and DT operation (fusion power up to 8.2 MW, ni0Ti0τE up to 1021 m-3 keV s). The role of the plasma edge is pointed out, as the power required to trigger an ITB is often higher than the H mode power threshold, leading to double barrier regimes. The presence of an H mode pedestal both modifies the ITB and induces edge bootstrap and ELM activity, which should be controlled to prolong such discharges. The operational procedure of optimization is then discussed, addressing the problems of ITB formation (power threshold, timing of the main heating phase, i.e. optimization of the target q profile, influence of the heating scheme, electron versus ion ITBs), ITB evolution (expansion of the ITB footpoint, H mode formation) and ITB termination (disruptive and/or 'soft' MHD limits). Finally, the crucial problem of the route to steady state for such OS discharges is addressed, both in terms of ITB sustainment and control within the stability domain and in terms of edge pedestal control by means of impurity injection. The impurity behaviour is found, and examples of high performance discharges sustained for several energy confinement times are given (βN = 1.95, H89 = 2.3, Pfusioneq ∼ 10 MW, QDTeq ∼ 0.4 sustained for ∼ 3 s). Extrapolation towards fully non-inductive current drive is discussed. (author)

Additional details

Publishing Information

Journal Title
Nuclear Fusion
Journal Volume
40
Journal Issue
6
Journal Page Range
p. 1113-1123
ISSN
0029-5515

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
31033739
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Descriptors DEI
JET TOKAMAK; MAGNETIC CONFINEMENT; MAGNETIC FIELD CONFIGURATIONS; MEETINGS; SHEAR; STEADY-STATE FUSION REACTORS
Descriptors DEC
CLOSED PLASMA DEVICES; CONFINEMENT; PLASMA CONFINEMENT; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES

Optional Information

Notes
26 refs, 14 figs