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Research Needs for Magnetic Fusion Energy Sciences - US Burning ...

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ELM-FREE HigH PERFORManCE<br />

stellarators can operate in high-per<strong>for</strong>mance, high-confinement discharge modes both with and<br />

without elms. edge localized modes are often observed in stellarator h-mode discharges, but the<br />

available data and understanding are more limited than in tokamaks at present. as in tokamaks,<br />

stellarator elms are associated with strong pressure gradients at the plasma edge, and act to<br />

flush out impurities. The appearance of stellarator elms depends sensitively on the edge rotational<br />

trans<strong>for</strong>m. an elm-free, high-density h-mode attained in stellarators exhibits good thermal<br />

confinement with low impurity confinement times. stellarator optimization may allow <strong>for</strong> good<br />

core confinement with edge conditions amenable to elm suppression. The application of non-axisymmetric<br />

fields in the edge region has been shown in some cases to suppress elms in tokamaks.<br />

research requirements<br />

• Understand the mechanisms of enhanced transport in the edge thought to be responsible<br />

<strong>for</strong> elm suppression with non-axisymmetric perturbations.<br />

• Understand impurity transport in stellarator discharges without elms that show low<br />

impurity accumulation. determine whether the elm-free hdh mode can extrapolate to<br />

a burning plasma.<br />

• high-per<strong>for</strong>mance Qs plasmas are needed to determine whether lower edge pressure<br />

gradients are compatible with large pressure gradients in the core.<br />

SuPERCOnDuCting StELLaRatOR COiLS<br />

high t c superconductors could have a large potential impact on fusion devices as identified in the<br />

Fesac “Priorities, Gaps, and opportunities” report, and is a focus of Thrust 7. second generation<br />

high-temperature superconductors (hts) offer many advantages <strong>for</strong> fusion magnets over present<br />

technology. This is especially true <strong>for</strong> stellarators. The conductors can have small curvature radii,<br />

advantageous <strong>for</strong> stellarator coils. demountable joints provide new possibilities <strong>for</strong> access and<br />

maintenance. Quench protection can be built into the magnet without large amounts of stabilizer.<br />

higher current densities, critical field, and broader temperature range ease engineering design<br />

and cryo-loads. novel manufacturing techniques are possible with the second-generation material,<br />

which might permit a direct application to an otherwise structural element. a staged program<br />

is needed to evaluate the suitability of hts <strong>for</strong> stellarator coils or flux shaping components.<br />

research requirements<br />

design and prototype work should be done so that, if advantageous, this technology could be applied<br />

to all fusion systems in the iteR-era.<br />

• Undertake an engineering analysis of an example stellarator coil to determine critical<br />

elements in an R&d strategy <strong>for</strong> application of high t c to stellarators.<br />

• carry out appropriate R&d through fabrication and testing of a model coil.<br />

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