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

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corporation of a sol wave-sheath code is necessary <strong>for</strong> quantitative work. edge physics transport<br />

and turbulence codes are available in which radiofrequency effects can be included.<br />

The action items are as follows: (1) Use improved diagnostic coverage to verify the strength and<br />

location of radiofrequency sheaths, confirming connection along b to the antenna. The associated<br />

sputtering should be quantified by spectroscopic measurements. (2) compare and verify existing<br />

radiofrequency sheath models; aid inclusion in boundary codes. (3) improve or develop models<br />

<strong>for</strong> parasitic power loss from radiofrequency antennas and launchers; develop methods <strong>for</strong> reducing<br />

the loss. (4) incorporate radiofrequency models in boundary codes and validate with diagnostic<br />

data. (5) incorporate radiofrequency sheath and loss models in antenna and propagation<br />

codes. (6) integrate boundary transport and turbulence, wall codes, and radiofrequency antenna<br />

and propagation codes to understand the interdependence (e.g., gas puffing to enhance radiofrequency<br />

coupling to the main plasma).<br />

4. Integrated experimental tests and development of innovative divertors<br />

While this section is brief, it nevertheless involves a major ef<strong>for</strong>t in testing and utilizing the building<br />

blocks of sections 1-3. complete physics understanding and validation of models in all boundary<br />

areas discussed will require significant operational time on confinement experiments. While<br />

dedicated test stands can better address validation of certain elements of the models (see Thrust<br />

10), more dedicated run time will be needed on existing machines to properly test integrated per<strong>for</strong>mance<br />

in a realistic environment.<br />

innovative divertor magnetic configurations such as the super-X and/or snowflake <strong>for</strong> reducing<br />

peak heat fluxes offer high payoff and should be tested. These configurations can be <strong>for</strong>med in<br />

existing devices without new magnetic coils. some snowflake configurations have already been<br />

made. The super-X may require installation of some extended divertor surfaces at larger major radius<br />

to accept the heat flux. Promising results of such tests should be followed by extensive analysis<br />

to optimize their implementation in future devices, and to ensure that all the functions of<br />

a divertor — power exhaust, acceptable impurities, and helium exhaust — can be per<strong>for</strong>med simultaneously<br />

in the very challenging environment of future fusion plasmas. other innovations<br />

related to divertor materials are given in Thrust 11.<br />

all operational scenarios and new device designs discussed in ReneW will require substantial input<br />

from the knowledge gained in this Thrust, to ensure that the boundary layer plasma will satisfactorily<br />

per<strong>for</strong>m the many functions required <strong>for</strong> high-power fusion devices. While the emphasis<br />

here has been on tokamak boundary plasma, every ef<strong>for</strong>t should be made to understand the range<br />

of device types where the data and models are applicable and how to extend them where needed.<br />

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