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

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can enter the plasma core and diminish its per<strong>for</strong>mance either through radiation, in the case of<br />

heavy first-wall materials such as tungsten, or through fuel dilution <strong>for</strong> light impurities such as<br />

beryllium or carbon. Progress is being made both in understanding the physics of radiofrequency<br />

sheath <strong>for</strong>mation and in designing ion cyclotron resonance heating antennas that can reduce<br />

sheath <strong>for</strong>mation. however, given the importance of ion cyclotron resonance heating to the success<br />

of iteR (since it is the only method that heats ions), the research ef<strong>for</strong>t needs to be intensified<br />

with dedicated experiments and validated simulations of the antenna-plasma interaction, including<br />

the physics of radiofrequency sheath <strong>for</strong>mation.<br />

Fueling: Fueling efficiency and density profile control require that iteR be fueled well beyond<br />

the separatrix. The means <strong>for</strong> doing this is pellet injection, where, <strong>for</strong> maximum efficiency, pellets<br />

are launched from the inner (high field) region of the iteR vessel. Predictive understanding<br />

of the density profiles achieved with this arrangement requires quantitative knowledge of pellet<br />

ablation and penetration physics, in the presence of energetic ions, as well as of particle transport.<br />

The issue is complicated by the burning plasma environment of iteR, which couples the density<br />

produced by pellets to the alpha particle production rate. The effect of pellets on elms (possibly<br />

beneficial if “pellet pacing” is effective in reducing the size of elms) and other mhd activity also<br />

requires further research to make reliable predictions of the efficacy of pellet fueling in iteR.<br />

Fueling by pellets offers the further advantage of reducing the tritium inventory by injecting tritium-rich<br />

pellets, while fueling with gas at the edge with deuterium (and impurities) to maintain<br />

optimal divertor conditions. it then should be possible to provide a degree of control over the burn<br />

in iteR by feedback control of the isotopic mix. The time scale over which the mix can be varied is<br />

an important consideration and this requires additional research in existing pellet-fueled devices.<br />

The overall particle control issue, which includes fueling, is critical <strong>for</strong> the sustainment of burning<br />

plasmas. Pumping, the introduction of radiating impurities, the introduction of unintentional<br />

impurities, the removal of helium, the fuel mixture and core fueling, and the radiating divertor<br />

and overall power handling all must be simultaneously achieved <strong>for</strong> the burn to be sustained.<br />

Heat Exhaust: managing the heat load, both during the nominal steady state and transients,<br />

represents one of the biggest challenges to iteR. The largest heat load is on the divertor targets<br />

and, at 5-10 mW/m 2 , is at the limit of what is technologically feasible, especially considering the<br />

difficult plasma environment. transient events such as elms and loss of detachment can severely<br />

limit the target lifetime. to extend the lifetime, research is needed on critical heat removal issues,<br />

including how to control the power flowing to the divertor through feedback. an additional issue<br />

is the viability of the plasma facing components after large-scale surface damage and loss of con<strong>for</strong>ming<br />

surface geometry (relative to the magnetic field) due to repetitive ablation/melt loss from<br />

elms. The physics of radiative divertor solutions — including effects of opacity, impurity radiation<br />

(and effect on the core), and momentum transfer — also needs elaboration to develop confidence<br />

in the projected per<strong>for</strong>mance of the divertor design <strong>for</strong> iteR.<br />

tritium Retention: Retention of tritium in first-wall components had been identified as a critical<br />

issue <strong>for</strong> iteR since the earliest days of the iteR design. The problem is especially acute <strong>for</strong><br />

carbon plasma facing components due to co-deposition, the tendency of carbon to <strong>for</strong>m difficult-<br />

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