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

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thE REvERSEd FiEld piNch<br />

introduction<br />

during the iteR era, the goal <strong>for</strong> Reversed Field Pinch (RFP) research as identified by the Fesac<br />

toroidal alternates Panel (taP) is to:<br />

Establish the basis <strong>for</strong> a burning plasma experiment by developing an attractive self-consistent integrated<br />

scenario: favorable confinement in a sustained high-beta plasma with resistive wall stabilization.<br />

The distinctive feature of the RFP configuration <strong>for</strong> its fusion application is that electrical current<br />

flowing in the plasma generates most of the confining magnetic field. The externally applied toroidal<br />

magnetic field is relatively small, about two orders of magnitude smaller than that in a tokamak<br />

with similar plasma current. This reduced external magnetic field requirement offers significant<br />

advantages <strong>for</strong> fusion application. For example, the RFP attains very high engineering<br />

beta (the ratio of the plasma pressure to the maximum magnetic field pressure at the magnets).<br />

smaller magnets are allowed, which could be constructed using normal conductors (nonsuperconducting).<br />

also, the plasma current provides large ohmic heating, reducing or perhaps eliminating<br />

requirements <strong>for</strong> complicated auxiliary plasma heating systems. While reduced external field underlies<br />

these potential advantages, it also leads to the primary scientific challenges <strong>for</strong> the RFP.<br />

magnetic fluctuations arise more easily without a large externally imposed stabilizing field, and<br />

this has an impact on both plasma stability and confinement quality. also, the steady-state sustainment<br />

of the RFP’s relatively large plasma current is challenging.<br />

Figure 5. The RFP magnetic configuration. The direction of the magnetic field, B, varies strongly within plasma<br />

as a result of the small externally applied toroidal field.<br />

The small external toroidal magnetic field yields a low value of the magnetic winding parameter,<br />

q, compared with configurations that employ a larger external toroidal field, such as the tokamak,<br />

st, and stellarator. This parameter measures the helical twist of the magnetic field lines in the<br />

plasma. Thus, the RFP also offers unique science opportunities <strong>for</strong> plasma stability and confinement<br />

that complements the parameter regime of high-q configurations.<br />

Scientific Contributions<br />

achieving the iteR-era goal will contribute significantly to fusion energy sciences and broader<br />

scientific disciplines. examples are: (1) understand transport processes from turbulence that is<br />

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