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current to toroidal magnetic<br />

field strength does<br />

that trick. Again, <strong>the</strong> field<br />

line lengths did not matter.<br />

These data are part <strong>of</strong> a<br />

growing body <strong>of</strong> evidence<br />

that self-regulatory heat<br />

transport mechanisms<br />

are at play, which tend<br />

to clamp <strong>the</strong> width <strong>of</strong> <strong>the</strong><br />

heat flux pr<strong>of</strong>iles at a critical<br />

scale-length value.<br />

The physics <strong>of</strong> <strong>the</strong>se<br />

processes is a subject<br />

<strong>of</strong> fur<strong>the</strong>r investigation.<br />

High-power microwave tube sources, which provide power to drive steady-state<br />

plasma current in Alcator C-Mod.<br />

Alcator C-Mod have uncovered important clues,<br />

including behaviors that appear counter-intuitive<br />

at first. One prevailing model holds that, as <strong>the</strong><br />

length <strong>of</strong> <strong>the</strong> magnetic field line becomes longer,<br />

<strong>the</strong> footprint should get wider; <strong>the</strong> heat has more<br />

time to spread out.<br />

To test this model, Alcator C-Mod prepared two<br />

plasmas: one with <strong>the</strong> usual footprints and one<br />

with an additional set <strong>of</strong> footprints, each having<br />

half <strong>the</strong> field line length. No significant change<br />

in footprint shape was seen. In o<strong>the</strong>r plasmas, field<br />

line lengths were varied by changing how tightly <strong>the</strong>y<br />

twist around <strong>the</strong> torus – changing <strong>the</strong> ratio <strong>of</strong> plasma<br />

Steady-state operation<br />

is generally considered<br />

to be an essential requirement for a practical fusion<br />

reactor. However, <strong>the</strong> confining magnetic<br />

field in most tokamaks such as Alcator C-Mod is<br />

produced in part by a toroidal current generated<br />

by magnetic induction (<strong>the</strong> ”poloidal” magnetic<br />

field component). This means that such tokamaks<br />

are inherently pulsed plasma confinement systems<br />

and are most likely unsuitable for an economical<br />

reactor application. In addition, non-inductive<br />

methods <strong>of</strong> driving <strong>the</strong> toroidal current in a tokamak<br />

are available and include injecting RF<br />

waves (or microwaves) and/or neutral beams.<br />

In addition, only a fraction <strong>of</strong> <strong>the</strong> total current<br />

needs to be supplied by external sources, since<br />

substantial current is<br />

also produced naturally<br />

by <strong>the</strong> plasma pressure<br />

gradient (<strong>the</strong> so called<br />

“bootstrap” current). Developing<br />

<strong>the</strong> scientific<br />

basis for steady-state tokamak<br />

operation using<br />

<strong>the</strong> injection <strong>of</strong> microwaves<br />

to supplement<br />

<strong>the</strong> self-generated current<br />

is a high priority<br />

within <strong>the</strong> Alcator C-Mod<br />

research program.<br />

Important progress toward<br />

<strong>the</strong> steady-state<br />

goal was made this year<br />

using <strong>the</strong> lower hybrid<br />

<strong>PSFC</strong> <strong>Progress</strong> <strong>Report</strong> 09–11 11

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