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1. magnetic confinement - ENEA - Fusione

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50<br />

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

<strong>1.</strong>4 FT3 Conceptual Study<br />

<strong>1.</strong>4.1 Introduction<br />

Table <strong>1.</strong>III - FT3 parameters<br />

The FT3 concept is a proposed<br />

upgrade of FTU, which would<br />

enable studies of sub-ignited<br />

plasma conditions in deuterium<br />

plasmas (Q equiv ≈1-5) with<br />

particular reference to the<br />

collective effects driven by the<br />

fast ions produced by ICRH.<br />

Therefore, FT3 would prepare<br />

the operational scenarios of a<br />

burning plasma experiment by investigating the approach to ignition in the presence<br />

of the relevant dynamics of fast ions.<br />

FT3 is similar to JET from the point of view of dimensionless parameters, but the<br />

expected fusion performances are much higher because of the<br />

higher <strong>magnetic</strong> field B (the triple product nTτ is proportional to<br />

B at fixed dimensionless parameters). Indeed, the expected fastparticle<br />

parameters in FT3 at maximum performance are closer to<br />

those of a burning plasma experiment than the parameters<br />

achievable on JET at maximum performance. Note also that FT3<br />

has greater shaping flexibility at maximum plasma current than<br />

JET.<br />

The large range of <strong>magnetic</strong> field values achievable in FT3<br />

includes the ITER <strong>magnetic</strong> field value, so the proposed device<br />

would be a natural test bed for the development of ITER<br />

diagnostics and of auxiliary heating systems such as ECRH.<br />

Table <strong>1.</strong>III reports the main engineering parameters.<br />

B(T)/I(MA) 8/6<br />

P aux (MW) (ICRH/ECRH/LH) 25 (20/3.2/6)<br />

R(m) <strong>1.</strong>3<br />

a(m)/b(m) 0.48/0.9<br />

κ/δ≅I=6MA <strong>1.</strong>8/0.6<br />

t flat-top (s) ≅8T 4<br />

Three main operational scenarios are envisaged: single X-point<br />

(fig. <strong>1.</strong>48) at 8 T/6 MA for investigating H-mode and ITB<br />

formation at high <strong>magnetic</strong>-field and density; limiter scenario at 8<br />

T/7 MA to study enhanced L-mode regimes; single X–point at 5T/2.4 MA for longpulse<br />

scenarios and advanced tokamak physics. H-mode plasmas are expected to<br />

achieve an equivalent Q between Q = 1 and Q = 2, whereas the formation of an ITB<br />

could allow an equivalent Q in the range Q=5.<br />

Fig. <strong>1.</strong>48 - FT3 single-null<br />

equilibrium at B=8 T and<br />

I= 6MA.<br />

<strong>1.</strong>4.2 Main objectives of the FT3 scientific programme<br />

• Investigation of fast-ion collective effects in the parameter range relevant for<br />

burning plasmas. The fast-particle concentration achievable with 20-MW ICRH is<br />

sufficient for studying the destabilisation of resonant collective modes, such as<br />

fishbones and energetic particle modes (EPMs), which are in principle the most<br />

dangerous fast-particle collective effects. Investigation of these effects in negative<br />

<strong>magnetic</strong> shear discharges at B = 5 T will allow a better understanding of the role of<br />

these instabilities in advanced scenarios. Note that these regimes are obtained on FT3<br />

at a slowing down time/energy <strong>confinement</strong> time ratio comparable to that of a<br />

burning plasma experiment.<br />

• Test of H-mode threshold at high <strong>magnetic</strong> field. FT3 could prove the validity of<br />

the most recent scaling law for the L-H threshold (fig. <strong>1.</strong>49), which predicts a lower<br />

threshold power on ITER than the IPB98 scaling. This would facilitate making a final<br />

decision on the auxiliary heating systems of ITER. Note that JET data are consistent<br />

with both expressions of the L-H threshold and cannot provide a definitive answer.

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