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1. magnetic confinement - ENEA - Fusione

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<strong>1.</strong> MAGNETIC CONFINEMENT<br />

23<br />

[<strong>1.</strong>19] A. A. Tuccillo et al.,<br />

Proc. 14 th Topical Conf. on<br />

Radio Frequency Power in<br />

Plasmas (Oxnard 2001),<br />

Vol. 595, p. 209<br />

[<strong>1.</strong>20] V. Pericoli-Ridolfini<br />

et al., Proc. 14 th Topical<br />

Conf. on Radio Frequency<br />

Power in Plasmas (Oxnard<br />

2001), Vol. 595, p. 245<br />

[<strong>1.</strong>21] V. Pericoli-Ridolfini<br />

et al., Study and<br />

optimisation of lower<br />

hybrid waves coupling<br />

in advanced scenario<br />

plasmas in JET, to be<br />

submitted to Plasma Phys<br />

Control. Fusion<br />

the q profile during the high phase of advanced-scenario plasmas.<br />

• Task Force S2 experiment aiming at steady-state ITBs.<br />

• Task Force M experiments on neoclassical tearing mode (NTM) stabilisation by<br />

LHCD and some experiments on the error field.<br />

The H and S2 activities were carried out in close collaboration with CEA and<br />

UKAEA.<br />

Task Force H<br />

<strong>1.</strong>1 Tokamak Physics<br />

The activity here consisted mainly in continuing LH coupling optimisation in<br />

relevant scenarios. After the success of the previous campaigns in 2000<br />

[<strong>1.</strong>19,<strong>1.</strong>20,<strong>1.</strong>21], efforts were concentrated on the utilisation of LH to actively control<br />

the q profile. As expected, LH proved to be very effective, both in the pre-heat phase,<br />

to optimise the target, and in the high power phase, to maintain the q profile, of<br />

advanced-tokamak plasmas. An example of the capability of LH to model the q<br />

profile is given in figure <strong>1.</strong>16. During plasma current ramp-up in the pre-heat phase<br />

of advanced scenario plasmas, the target q profile can be changed from weakly<br />

reversed to deeply reversed by adjusting the power level. This tool has made it<br />

possible to lower the power threshold of electron ITBs, and with the improvement in<br />

LH wave coupling, more than 3 MW can be routinely coupled in H-mode in ITB<br />

plasmas.<br />

Task Force S2<br />

[<strong>1.</strong>22] F. Crisanti, et al.,<br />

The new LHCD capability strongly accelerated the progress of Task Force S2. Quasi<br />

JET quasistationary<br />

steady-state ITBs time limited only by technical constraints were achieved, and full<br />

internal-transportbarrier<br />

operation with<br />

CD was obtained during the whole high-performance phase of <strong>1.</strong>8-MA ITB<br />

discharges [<strong>1.</strong>22]. Later on during C4, the <strong>ENEA</strong> collaboration was extended to<br />

active control of the<br />

experiments on feedback control of pressure and temperature profiles by using,<br />

pressure profile, accepted<br />

for publication on<br />

respectively, neutral beam and ion cyclotron waves [<strong>1.</strong>22]. Figure <strong>1.</strong>17 reports the<br />

time evolution of a few quantities characterising one of the longest ITB discharges<br />

Phys. Rev. Lett.<br />

(q 95 ≈6.0, β p ≈<strong>1.</strong>1, β N ≈<strong>1.</strong>7, β T ≈<strong>1.</strong>%, B T =3.4 T and I p =2 MA). In this discharge, an<br />

electron ITB is triggered at the beginning of LH coupling. The ion ITB forms<br />

immediately after neutron beam injection (NBI) and ICRH. Both barriers disappear<br />

when the additional power is switched off and are time limited only by JET<br />

hardware constraints. The loop voltage close to zero and the internal <strong>magnetic</strong><br />

inductance practically<br />

constant all over the highpower<br />

phase indicate a<br />

EFIT + MSE at 44.4S<br />

B T = 2.6 T<br />

5<br />

51164<br />

possible “freezing” of the<br />

51465<br />

CD profile due to LHCD.<br />

51466<br />

The electron barrier lasts<br />

P LH = 2.2 MW<br />

about 37 energy <strong>confinement</strong><br />

times and the ion<br />

Fig. <strong>1.</strong>16 - Control of q<br />

4<br />

51467<br />

profile with LHCD<br />

barrier about 27. The<br />

preheating in the<br />

duration of the ITB is,<br />

optimised shear scenario.<br />

however, comparable with<br />

Weakly to deeply 3<br />

the current resistive<br />

reversed q profile as a<br />

diffusion time.<br />

function of LHCD power.<br />

profile<br />

2<br />

2.0<br />

P LH = <strong>1.</strong>1 MW<br />

2.5<br />

3.0<br />

R maj (m)<br />

3.5 4.0<br />

In-depth analyses aimed at<br />

understanding turbulencereduction<br />

mechanisms were<br />

performed and reported at<br />

several conferences, e.g. the<br />

2001 EPS and APS. The

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