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

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tHEME 3: taMiNG tHE PLaSMa-MatERiaL iNtERFacE<br />

introduction<br />

ScopE aNd FocuS<br />

The hot plasma in the core of a fusion energy device must interact with low-temperature material<br />

walls. That interaction is mediated by a thin plasma layer called the scrape-off layer (sol). many<br />

of the recent improvements in plasma core per<strong>for</strong>mance have been enabled by either improved<br />

understanding of the sol or improved plasma facing components (PFcs). The report of the Priorities,<br />

Gaps and opportunities Panel, or “Greenwald Report” 1 , identified three major issues at<br />

the plasma-material interface. We must “understand and control all of the processes which couple<br />

plasma and nearby materials” (issue 8). We must “understand the materials and processes that<br />

can be used to design replaceable components which can survive the enormous heat, plasma and<br />

neutron fluxes without degrading the per<strong>for</strong>mance of the plasma or compromising the fuel cycle”<br />

(issue 9). We must “establish the necessary understanding of plasma interactions, neutron loading<br />

and materials to allow design of RF [radiofrequency] antennas and launchers, control coils, final<br />

optics and any other diagnostic equipment which can survive and function within the plasma<br />

vessel” (issue 10). a total of nineteen gaps in knowledge was identified <strong>for</strong> the three issues.<br />

at least a dozen new facets of scrape-off layer behavior have been uncovered over the past decade.<br />

This improvement in understanding has been accomplished through a combination of new diagnostics<br />

(edge Thomson scattering, fast camera imaging), improved edge models (coupled fluid and<br />

neutral codes), and more dedicated plasma operation <strong>for</strong> edge diagnosis. several of these new facets<br />

have caused a major alteration to the design of iteR. The remaining uncertainty in the scaling<br />

of the power scale-length in the scrape-off layer has placed very tight constraints on the design<br />

of iteR components.<br />

Plasma facing components have increased significantly in heat flux capability in the last decade<br />

due to new materials (carbon fiber composite), improved design (protection of leading edges and<br />

better shaping relative to plasma flux surfaces), surface conditioning (boronization, helium glow<br />

cleaning, high-temperature baking), and in some cases active cooling. laboratory studies and<br />

limited application to fusion devices have proven the capability of water-cooled plasma facing<br />

components to achieve the heat removal required <strong>for</strong> iteR. There is an ongoing debate about the<br />

choice of plasma facing materials <strong>for</strong> iteR with some advocating an all tungsten option while others<br />

argue <strong>for</strong> all graphite, but the baseline PFcs <strong>for</strong> deuterium-tritium (d-t) operation have only<br />

beryllium and tungsten.<br />

long pulse radiofrequency antennas and launchers have been operated at high power on the tore<br />

supra device where pulse lengths are measured in minutes. improvements in feedback control<br />

have yielded more stable radiofrequency heating in existing devices. such operation has revealed<br />

interesting new physics in the plasma edge. electron cyclotron resonance heating has been used<br />

1 “Priorities, Gaps and Opportunities: Towards A Long-Range Strategic Plan For <strong>Magnetic</strong> <strong>Fusion</strong><br />

<strong>Energy</strong>” Report to FESAC Oct 2007, M. Greenwald, Chairman.<br />

123

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