09.12.2012 Views

1 - Nuclear Sciences and Applications - IAEA

1 - Nuclear Sciences and Applications - IAEA

1 - Nuclear Sciences and Applications - IAEA

SHOW MORE
SHOW LESS

You also want an ePaper? Increase the reach of your titles

YUMPU automatically turns print PDFs into web optimized ePapers that Google loves.

E6950(Bi=4.0T)<br />

E6956(Bt = 2.7T)<br />

°46 5.0 5.5 6.0 6.5 7.0 7.5<br />

TIME(S)<br />

<strong>IAEA</strong>-CN-50/A-V-1 267<br />

h-> IMPROVED<br />

4.5 5.0 5.5 6.0 65 70 75<br />

TIME(S)<br />

FIG. 1. Comparison ofl MA discharge waveforms with <strong>and</strong> without improved confinement. The thick<br />

lines st<strong>and</strong> for traces of an enhanced shot (E6950; B, = 4T, q^f "3.7) <strong>and</strong> thin ones for a low-q shot<br />

(E6956; B, = 2.7T, qtff » 2.4).<br />

There is, however, a threshold for the heating power (—15 MW) to achieve the<br />

improvement.<br />

The IDC regime is easily obtained at high B,, whereas clear H-phases are<br />

observed only in low B, discharges. Figure 2 shows the points where IDC regime,<br />

L/H transitions <strong>and</strong> ELMs appear in the domain of line averaged electron density <strong>and</strong><br />

absorbed power. L/H transitions were observed in low density discharges for Bt<br />

around 3 T. The IDC regime sets in afterwards at higher electron densities. When<br />

Bt is higher, the IDC regime starts at lower electron densities. The threshold i^<br />

increases with power in both cases. Since the connection length of the magnetic field<br />

lines from the plasma edge to the divertor plates increases with Bt, these findings<br />

suggest that the IDC regime is related to the formation of dense <strong>and</strong> cold divertor<br />

plasmas [9, 10]. The time evolution of the divertor plate temperature is measured<br />

with an infrared camera. An example for these measurements is shown in Fig. 3. It<br />

should be noted that the rate of temperature increase drops when the IDC regime sets<br />

in around 5.7 s. The heat flux onto the divertor plates which is evaluated with a 1-D<br />

heat inverse conduction code decreases during the IDC regime. The total power load<br />

at 6.7 s is estimated to be about 4 MW, on the assumption that the heat flux profile<br />

is similar to the temperature profile. The values of the radiation power from main<br />

<strong>and</strong> divertor plasmas are about 4 MW <strong>and</strong> 9 MW, respectively. Thus, the total

Hooray! Your file is uploaded and ready to be published.

Saved successfully!

Ooh no, something went wrong!