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1 - Nuclear Sciences and Applications - IAEA

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<strong>IAEA</strong>-CN-50/A-HI-2 167<br />

near the first stability boundary. These preliminary results suggest that the pressure<br />

gradients are lower than would be required by the bifurcation model of<br />

Bishop [17] . Nevertheless they indicate that the edge pressure gradients in the<br />

H-mode are sufficiently steep that ideal ballooning stability becomes relevant.<br />

Furthermore the current density parameter A is found to be consistent with the<br />

critical value needed for coalescence.<br />

3.5 Divertor plasma<br />

The plasma in the vicinity of the X-point target plates (divertor plasma) has<br />

been investigated with an array of eight Langmuir probes mounted in the target<br />

plates (see inset in Fig. 6), with a reciprocating Langmuir probe (at R=3.25 m),<br />

<strong>and</strong> with a 2-dimensional view of the radiation from the divertor region.<br />

Fig. 6 shows profiles of density, temperature <strong>and</strong> ion saturation current in front<br />

of the target plates for a 4.6 MA discharge (OH <strong>and</strong> H-phase with PNBI=14 MW).<br />

Although a single-null discharge, the inner divertor plasma is colder <strong>and</strong> denser<br />

than the outer. More power is carried to the outer divertor, suggesting that the<br />

main source of power flow into the scrape-off layer is in the vicinity of the outer<br />

mid^plane, ie, closer to the outer divertor target. The unequal temperatures lead<br />

to thermo-electric currents in the scrape-off layer [18 l Current densities<br />

g 10 5 AnT 2 have been measured during the H-phase (see Fig. 6) corresponding<br />

to more than 10% of the mean current density in the discharge. The scrape-off<br />

layer current flows from outer to inner divertor <strong>and</strong> returns through the target<br />

plates, thus flowing in the same direction as the plasma current.<br />

The power estimated to be carried by plasma to the target plates increases<br />

from 0.8MW in the ohmic phase to 1.9MW at the end of the H-phase. For most<br />

of the discharge, i.e. L <strong>and</strong> H-phases, this is about 15% of (Ptotal-dWdia/df)<br />

but about 25% during the ohmic phase.<br />

Profiles with the reciprocating probe in the scrape-off layer agree reasonably<br />

well with those at the divertor target. Preliminary results for two or three pulses<br />

show that the radial electric field, just inside the separatrix, Er = - (d Vp/asma)/dr<br />

is negative in the ohmic phase <strong>and</strong> about + 5 kVnT 1 with H-mode. This result,<br />

if substantiated, would agree with the prediction of Itoh <strong>and</strong> Itoh [19] .<br />

The collisionality of the divertor plasma may have a bearing on whether an<br />

H-mode can be achieved. Two aspects of collisionality are considered: Coulomb<br />

collisions with electrons, <strong>and</strong> ionisation of neutral particles in the divertor plasma.<br />

For Coulomb collisions, the Coulomb mean free path, Xee, is compared with<br />

the distance Ln in the divertor measured along a field line from the target to<br />

the X-point. With the X-point typically 0.10m from the target <strong>and</strong> a pitch angle<br />

of the field lines of ~ 1°, Ln«6m. Fig.7 shows probe measurements of Te<br />

plotted against ne on a logarithmic scale. The straight line represents Xee = 6 m:

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