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

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calized field errors that can cause wall locking of tearing modes, as shown in RFX-mod and mst.<br />

RFX-mod experiments have also established that locking of tearing mode phases to the wall can<br />

be mitigated by appropriate feedback using the full-coverage coil set.<br />

research requirements<br />

Present experiments suggest that it is possible to operate a RFP without a very conducting wall.<br />

however, key questions remain, and the optimal control system has not been identified. Will<br />

coils located inside the vessel be able to mitigate phase locking to the wall, optimize the plasma<br />

shape and help <strong>for</strong> power handling (as in iteR)? Will it be necessary to include special flux loops<br />

to control m=0 modes (m is poloidal mode number)? Will ad hoc saddle coils be able to compensate<br />

<strong>for</strong> the residual error fields due to the unavoidable asymmetries of the magnetic boundary?<br />

certain types of coils may be optimal <strong>for</strong> different instabilities. nonlinear coupling between m=1<br />

and m=0 poloidal mode makes control of both harmonics important. separate coils optimized <strong>for</strong><br />

m=0 control may be needed. The toroidal field coil set in RFX-mod could in principle provide significant<br />

m=0 mode control, but the precision of the currently installed power supply units is limited.<br />

in both RFX-mode and extrap t2R, the issue of sideband aliasing (unwanted perturbations<br />

in other modes) has been observed and improvements in control have been obtained by reducing<br />

it either by increasing the number of actuators (t2R) or by removing it from the measurements in<br />

real time (RFX-mod). it is vital to understand the required minimum number of control coils, and<br />

how advanced control algorithms can surmount issues such as sideband aliasing.<br />

The development of accurate models is essential <strong>for</strong> understanding the behavior of the present<br />

control systems and <strong>for</strong> predicting the per<strong>for</strong>mance and control requirements of future devices.<br />

several approaches are possible. an existing model of the electromagnetic boundary that includes<br />

simplified transfer functions <strong>for</strong> the feedback-controlled current power supply units in a multiinput,<br />

multi-output paradigm reveals the necessity to better understand and model the mutual<br />

couplings of the feedback coil hardware. in the near term, merging the electromagnetic code cariddi<br />

with the maRs code can advance this issue. The development of a full simulator of an RWm<br />

control system <strong>for</strong> existing devices will also allow testing different kinds of model-based control<br />

approaches, where standard Pid controllers will be replaced by more complex state-space controllers,<br />

and which may also take into account the 3-d structure of the magnetic boundary. a parallel<br />

approach to RWm control modeling is based on the development of a more complete physics model<br />

of the plasma in a simplified geometry, taking into account plasma pressure, compressibility,<br />

inertial, dissipation and longitudinal plasma rotation. in addition to RWm modes, optimization<br />

of the magnetic boundary <strong>for</strong> the control of tearing modes is important, <strong>for</strong> example, identifying<br />

the ideal non-axisymmetric de<strong>for</strong>mation of the last closed magnetic surface.<br />

SELF-COnSiStEnt REaCtOR SCEnaRiOS<br />

in addition to the integration of current sustainment and improved confinement, a self-consistent<br />

scenario must also integrate RWm control and plasma boundary control to achieve high-per<strong>for</strong>mance<br />

RFP discharges and establish the knowledge base <strong>for</strong> a burning plasma experiment. The<br />

RFX-mod and extrap t2R facilities have capability to begin addressing the optimization of RWm<br />

control, but not <strong>for</strong> issues such as requirements on the proximity of feedback coils to the plasma<br />

surface. mst can apply current profile control and possibly enhance plasma pressure, but cannot<br />

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