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

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heating, fueling, and power exhaust in burning plasma conditions<br />

auxiliary Heating: The auxiliary heating and current drive schemes planned <strong>for</strong> initial operation<br />

of iteR feature 20 mW of electron cyclotron power at 170 Ghz, 20 mW of ion cyclotron power<br />

at 50 mhz and 33 mW of neutral beam injection at 1 mev energy. issues related to electron<br />

cyclotron resonance heating and neutral beam injection are largely technical. although a 1 mW<br />

prototype gyrotron operating at 170 Ghz has been successfully tested <strong>for</strong> long pulse, the technology<br />

is still in its infancy, and the reliability of 24 such tubes operating simultaneously to deliver<br />

the required 20 mW of electron cyclotron power needs confirmation. although our iteR partners<br />

are adequately addressing gyrotron technology <strong>for</strong> iteR, the absence of a Us ef<strong>for</strong>t on gyrotrons<br />

<strong>for</strong> iteR raises a concern about the basis <strong>for</strong> the Us to proceed toward a demo, which in all probability<br />

will require electron cyclotron resonance heating technology. in the case of neutral beam<br />

injection, many years of ef<strong>for</strong>t have failed to reach 1 mev beams at the requisite current density.<br />

There are plans to build a full test stand in europe, and an aggressive attack on this issue is underway.<br />

neutral beam injection has been the most reliable and widely used heating and current drive<br />

source in the international tokamak ef<strong>for</strong>t and was used to create record-high ion temperatures in<br />

tFtR (see Figure 8). consequently, extrapolations of the tokamak database in critical areas such<br />

as torque generation, rotational control of stability, fast ion physics, and active beam diagnostics<br />

are considered more credible than <strong>for</strong> other heating and current drive methods.<br />

ion cyclotron resonance heating is also effective in heating tokamak plasmas, as shown in the example<br />

from alcator c-mod (see Figure 9), where it has been used to produce record plasma pressures.<br />

however, unlike electron cyclotron resonance heating and neutral beam injection, where<br />

the technology is still in development but the heating physics is relatively straight<strong>for</strong>ward, ion cyclotron<br />

resonance heating is based on relatively secure technology with some uncertainty in the<br />

physics. The main issue is that ion cyclotron antennas must be in contact with the edge or scrapeoff<br />

layer (sol) plasma so that the antenna impedance can be matched at antenna voltages below<br />

breakdown levels, typically 50 kv. consequently, ion cyclotron resonance heating antennas <strong>for</strong>m<br />

radiofrequency sheaths in the scrape-off layer that can accelerate ions into the plasma facing materials<br />

at energies of a few 100 ev, well in excess of sputtering thresholds. sputtered impurities<br />

T i (keV)<br />

50<br />

40<br />

30<br />

20<br />

10<br />

0<br />

2.6<br />

2.8 3.0 3.2<br />

3.4<br />

Major Radius (m)<br />

4.1<br />

Figure 8. Creation of record high ion temperatures<br />

(> 40 keV) in TFTR by neutral beam heating.<br />

(Figure courtesy of E. Synakowski and R.E. Bell;<br />

<strong>for</strong> a related article, see D. Mansfield et al., Phys.<br />

Plasmas 3 [1996] 1892.)<br />

4.2<br />

4.3<br />

4.4<br />

Time (sec)<br />

4.5<br />

4.6<br />

4.7<br />

43<br />

Figure 9. RF power at the ion cyclotron frequency in<br />

an Alcator C-Mod plasma discharge increased the<br />

plasma pressure to 1.8 atmospheres, the same pressure<br />

at which ITER will operate. (Figure reproduced<br />

from S. Scott et al., Nucl. <strong>Fusion</strong> 47 [2007] S598.)

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