1. magnetic confinement - ENEA - Fusione
1. magnetic confinement - ENEA - Fusione
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.