1 GA A26242 COMPREHENSIVE CONTROL OF RESISTIVE WALL MODES IN DIII-D ADVANCED TOKAMAK PLASMAS by M. OKABAYASHI, I.N. BOGATU, T. BOLZONELLA, M.S. CHANCE, M.S. CHU, A.M. GAROFALO, R. HATCHER, Y. IN, G.L. JACKSON, R.J. LA HAYE, M.J. LANCTOT, Y.Q. LIU, T.C. LUCE, L. MARRELLI, P. MARTIN, G.A. NAVRATIL, H. REIMERDES, E.J. STRAIT, H. TAKAHASHI, and A.S. WELANDER SEPTEMBER 2008
2 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.
3 GA A26242 COMPREHENSIVE CONTROL OF RESISTIVE WALL MODES IN DIII-D ADVANCED TOKAMAK PLASMAS by M. OKABAYASHI,* I.N. BOGATU, T. BOLZONELLA, # M.S. CHANCE,* M.S. CHU, A.M. GAROFALO, R. HATCHER,* Y. IN, G.L. JACKSON, R.J. LA HAYE, M.J. LANCTOT, Y.Q. LIU, T.C. LUCE, L. MARRELLI, # P. MARTIN, # G.A. NAVRATIL, H. REIMERDES, E.J. STRAIT, H. TAKAHASHI,* and A.S. WELANDER This is a preprint of a paper to be presented at the 22nd IAEA Fusion Energy Conference, October 13-18, 2008, in Geneva, Switzerland, and to be published in the Proceedings. *Princeton Plasma Physics Laboratory, Princeton, New Jersey. FAR-TECH, Inc., San Diego, California. # Corsorzio RFX, Italy. Columbia University, New York, New York. UKAEA, Culham, United Kingdom Work supported in part by the U.S. Department of Energy under DE-AC02-76CH03073, DE-FG03-95ER54309, DE-FC02-04ER54698, DE-FG02-03ER83657, and DE-FG02-89ER53297 GENERAL ATOMICS PROJECT SEPTEMBER 2008
4 IN DIII-D ADVANCED TOKAMAK PLASMAS M. Okabayashi, et al. Comprehensive Control of Resistive Wall Modes in DIII-D Advanced Tokamak Plasmas M. Okabayashi 1), I.N. Bogatu 2), T. Bolzonella 3) M.S. Chance 1), M.S. Chu 4), A.M. Garofalo 4), R. Hatcher 1), Y. In 2), G.L. Jackson 4), J.S. Kim 2), R.J. La Haye 4), M.J. Lanctot 5), Y.Q. Liu 6), T.C. Luce 4), L. Marrelli 3), P. Martin 3), G.A. Navratil 5), H. Reimerdes 5), E.J. Strait 4), H. Takahashi 1), and A.S. Welander 4) 1) Princeton Plasma Physics Laboratory, Princeton, New Jersey, USA 2) FAR-TECH, Inc., San Diego, California, USA 3) Consorzio RFX, Italy 4) General Atomics, San Diego, California, USA 5) Columbia University, New York, New York, USA 6) UKAEA, Culham, UK contact of main author: Abstract. The resistive wall mode (RWM) and neoclassical tearing mode (NTM) have been simultaneously suppressed in the DIII-D for durations over 2 seconds at beta values 20% above the no-wall limit with modest electron cyclotron current drive (ECCD) and low plasma rotation. The critical plasma rotation was significantly lower than reported at the IAEA FEC in However, even in this stabilized regime, stable steady-state operation is not unconditionally guaranteed. Various localized MHD activities such as edge localized modes (ELMs) and fishbones begin to couple to the RWM branch near the no-wall limit. Feedback is useful to improve the stability. Simultaneous operation of slow dynamic error field correction and fast feedback suppressed the ELM-induced RWM at high normalized beta. The result implies that successful feedback operation requires careful control of residual RWMs. The effectiveness of feedback operation was demonstrated using a reproducible current-driven RWM. The present findings are extremely useful in the challenge of control of RWM and NTM in the unexplored physics territory of burning plasmas in ITER. 1. Introduction Comprehensive control of the resistive wall mode (RWM) is a prerequisite for achieving steady-state commercial fusion reactors based on the Advanced Tokamak concept . The RWM is an ideal-kink mode branch, excited due to the finite resistivity of the external wall surrounding the plasma when the plasma pressure expressed by exceeds the ideal MHD nowall stability limit, no wall, where is defined as plasma pressure divided by the confining magnetic pressure. The existence of high beta regimes stable to the RWM and above the nowall beta limit was successfully demonstrated at low plasma rotation in DIII-D and JT-60U [2 4]. Another global mode, the 2/1 neoclassical tearing mode (NTM), becomes a performance limiting instability at high N [ /(I p /ab T ) ] by lowering confinement and leading to N collapse. Recently, the NTM threshold in DIII-D was found to depend on plasma rotation near the no-wall limit . Numerical simulation has predicted that the NTM can be excited just above no-wall limit without any seed island . When the plasma rotation is as low as expected in ITER, it is possible that these dependences of the RWM and NTM onset on the plasma rotation add to the complexity for identifying and controlling the RWM. In RWM stability experiments on DIII-D, electron cyclotron current drive (ECCD) has been applied on the q=2 surface to suppress the NTM. Both the RWM and NTM have been simultaneously suppressed for over 2 seconds. The critical rotation for RWM stability was significantly lower than reported in [2,3]. However, even in this stabilized regime, stable steady-state operation is not unconditionally guaranteed. In advanced tokamak plasmas with high q operation, the q=2 fishbone instability excites RWM at low rotation (Fishbone-driven RWM). Even with high plasma rotation, ELM-induced RWM has caused N collapse (ELMdriven RWM). Feedback is useful to improve the stability. In the DIII-D facility, two coil systems are available for separate feedback functions, one with internal I-coils for fast time response GENERAL ATOMICS REPORT GA-A
5 M. Okabayashi, et al. IN DIII-D ADVANCED TOKAMAK PLASMAS ( FB < ~ w ) and the other with external C-coils for slow time response ( FB > ~ w ), where FB is the feedback time constant and w is the resistive wall time. Simultaneous operation of fast feedback and slow dynamic error field correction is a promising approach . A hypothesis is proposed that the finite amplitude of a residual RWM increases the complexity of the feedback process. A possible process of forming residual RWM is the resonant field amplification of unknown error fields. The result implies that successful feedback operations require careful control of residual RWM. The complexity of feedback operation at high N could also be caused by more fundamental issues such as mode non-rigidity under the presence of non-axisymmetric field, which was studied using the NMA code . The reproducible current-driven RWM (at very low N ) was utilized to reveal details of feedback process. 2. RWM Stability in the NTM Suppressed Plasmas by ECCD Pre-emptive NTM suppression by ECCD  was applied to high N plasmas 20% above no-wall limit, N.no-wall (~2.5l i ), which targets were used previously for low rotation high N plasma exploration . The ECCD power of 2 MW, moderate compared to the MW NBI injected power, was sufficient to successfully suppress the NTM. Figure 1 shows a typical discharge with ECCD- NTM suppression where a global mode appeared 500 ms after the ECCD was terminated. The suppression of the NTM made discharges routinely stable at low rotation. A low rotation target was developed by adjusting the combination of co- and counter-nbi power levels to produce plasma rotations as low as possible with a preset-value of N. A few discharges were terminated by modes with near zero mode frequency, when the plasma rotation became very low. The FIG. 1. Long duration RWM/NTM free operation at high N by means of ECCD NTM suppression along with RWM control by modest plasma rotation at q~2 (~10 20 km/s, corresponding to A ~ 0.1% 0.2%, where A is Alfvenic time constant). (a) N and the estimated no-wall limit N.no-wall 2.5 l i, (b) the plasma rotation at q~2, (c) the n=1 B p magnitude. RWM grew, coincident with the ELM event, with a growth time of ~10 ms, the same order of magnitude as the wall time, w (ELM-driven RWM). This growth time is consistent with the growth time of RWM theory prediction and similar to the ones previously reported . Most of the n=1 MHD activity was excited at lowest rotation several hundred milliseconds after the ECCD was turned off. These modes appeared either with a mode frequency of a few khz or near-zero. When the mode was rotating, the mode frequency was near the plasma rotation frequency at q=2, implying that the mode is the NTM. An interesting question arises as to whether or not the non-rotating mode belongs to the NTM or RWM branch. The poloidal mode structure of the non-rotating mode was compared to that of the rotating mode (after it had locked) using a poloidal array of saddle loops, and they were found to be virtually identical, suggesting that the rotating and non-rotating modes are the same mode. Additional information is available from the response of this mode to feedback with proportional-only gain. Figure 2(a,b) shows examples of the mode growth excited with/without feedback. For both cases, the ECCD was shut off at 3000 ms. Without feedback [Fig. 2(a)], a rotating mode was excited around t = 3200 ms with a growth time 1/ ~ 60 ms 2 GENERAL ATOMICS REPORT GA-A26242
6 IN DIII-D ADVANCED TOKAMAK PLASMAS M. Okabayashi, et al. and with feedback [Fig. 2(b)], the onset of non-rotating mode was around t = 3600 ms with the growth time of ~50 ms. Dependence of the growth time on a feedback parameter, toroidal phase shift, between the observed mode and the feedback response, FB, is shown in Fig. 2(c). The growth time does not show any preference to the feedback being on or off, the feedback phase shift, or non-rotating/rotating mode. The growth time of the non-rotating case comparable to that of the rotating mode, and considerably longer than that of the low-rotation ELM-driven RWM. These results support a hypothesis that the final collapsing global mode, as shown in Fig.1(c), is not a RWM but more likely a NTM growing in the absence of rotation. FIG. 2. The mode amplitude along with a B p sensor signal (a) without feedback, (b) with feedback. (c) The growth time vs a feedback parameter, toroidal phase shift FB. The growth time was averaged over the time period of B p from 5 to10 Gauss. The results marked by circles were rotating modes and the ones marked with squares were non-rotating modes. Two shots without feedback (marked with stars) are also included for comparison. The plasma conditions achieved using NTM suppression with ECCD are summarized in Fig. 3(a) in the dependence of C [=( no-wall )/( ideal-wall no-wall )] on plasma rotation at q~2. With the appearance of the rotating mode, the critical rotation was similar to the results reported at the IAEA FEC in When the mode was excited as a non-rotating mode, the critical rotation at q=2 was lower and the flatness of the rotation profile at mode onset was significantly different from the one previously reported except very near the edge [Fig. 3(b)]. These results imply the possible existence of RWM suppression mechanisms even when the plasma rotation is totally absent as proposed in . Another possibility is that the edge electric field, which remains similar in these experiments, can be a determining factor of the RWM onset. Since most of the nonrotating modes were excited with feedback applied, it is possible that the feedback had some impact on the final stage toward zero rotation. However, as shown in Fig. 2(c), there was not much definitive dependence of the growth time on the feedback parameters or the presence/absence of feedback. FIG. 3. Achieved C vs plasma rotation at q=2 surface. With ECCD NTM suppression, critical rotation at the q=2 surface was near zero. The data were with a rotating mode (circles) and non-rotating mode (squares). Shots without feedback (stars) include several from 2006 for comparison. (b) The rotation profile (#132270) was considerably lesspeaked compared with the one (#125709) reported in IAEA GENERAL ATOMICS REPORT GA-A
7 M. Okabayashi, et al. IN DIII-D ADVANCED TOKAMAK PLASMAS 3. MHD-driven RWM Stability and Feedback Various MHD events occur in high N discharges, producing a wide range of toroidal and poloidal magnetic field patterns. When the RWM stability condition becomes marginal at high beta and low rotation, these fields can interact directly or indirectly with the RWM mode pattern, leading to a rapid, forced excitation of RWM on the time scale of the driving MHD event (MHD-driven RWM). Quite often, the MHD-driven RWM amplitude can be significant, however, the mode itself can remain in marginally-stable regime. On the other hand, this MHD-driven RWM decays very slowly over tens of milliseconds, potentially leading to N collapse. Feedback is useful to reduce the mode amplitude before any serious impact takes place q=2-fishbone-induced RWM Stability and Feedback Frequency (khz) n=1 B p Amplitude (Gauss) n=1 B p Amplitude (Gauss) B p Integrated Mirnov (Gauss) FIG. 4. (a) MHD spectrum of q=2 fishbone-like activity with high (#132270) and low (#131129) rotation. (b) the amplitude, (c) the rotation of plasma at q~2. The detail of RWM onset (#131129) was shown in (d) the mode amplitude, (e) the Mirnov signal, (f) the ECE signal at ~0.5. Sharp distortion of signal T e (dotted lines) coincided with the fast change of Mirnov signal. In the time evolution of the advanced tokamak target, the discharge trajectory passes through regimes vulnerable to various MHD global modes. The m=2/n=1 q=2-fishbone RWM is one of them when q min is ~2. The fishbone at low plasma rotation is quite different from the traditional fishbone of high rotation plasmas. As shown in Fig. 4, when the plasma rotation was kept high enough (e.g., # at t ~ 1500 ms) the fishbone bursting period caused little impact on the discharge time evolution (time traces of plasma parameters of # in Fig. 1). When the plasma rotation became lower (at t ~ 1900 ms of #131129), the fishbone frequency was reduced, leading to several tens of Gauss RWM onset and N collapse at t ~ 2000 ms. Before the RWM onset took place, the time-integrated Mirnov signal, B p, was strongly distorted [Fig. 4(e)]. The ECE T e ( ~0.5), detected at the same toroidal angle as where the Mirnov loop is located, showed a sharp drop at the time corresponding to the integrated Mirnov signal distortion [Fig. 4(f)]. The source of the distortion observed externally is related to the internal structure located around ~0.5, which suggests a snake-like magnetic island . This snake-like magnetic island is a possibility to enhance the interaction of the (internal kink driven) fishbone and the marginally-stable external kink, exciting the RWM. Another possibility is that the q=2 area is covered by both the q=2 fishbone and external kink, allowing these mode structures to couple when the rotation of fishbone approaches zero. An interesting result is seen with the application of feedback. Without feedback [Fig. 5(a)], a nearly stationary mode with amplitude ~30 Gauss remains after the last cycle of the q=2 fishbone. When the feedback was applied [Fig. 5(b)], a large portion of the mode, dc-like slow n=1 component, was suppressed. However, some rotating mode of less than 1 khz Rot (km/s) (d) (e) (f) Fishbone-snake Time (ms) GENERAL ATOMICS REPORT GA-A26242
8 IN DIII-D ADVANCED TOKAMAK PLASMAS M. Okabayashi, et al. persisted along with the snake-like distortion seen on the ECE T e, indicating that the slow component is a remnant of the internal kink. This slow mode interfered with the feedback process, which gradually requested inordinately-high coil currents. FIG. 5. n=1 fishbone-driven RWM: (left column) without and (right column) with feedback. Application of simple feedback with proportional-gain-only reduced the slow component of q=2 fishbone-driven RWM. (a) B p sensor signal, (b) T e at ~0.5 (toroidal angle = 60 ), (c) Mirnov signal (toroidal angle = 67 ) ELM-induced RWM in High Rotation Plasmas: Stability and Feedback As reported previously , in the high plasma rotation regime the RWMs driven by type-i ELMs are modest with magnitude of 3 10 Gauss and decay times comparable to the resistive wall time scale. Simple feedback operation with proportional-gain-only reduced the RWM amplitude within a fraction of the wall time (~1 ms). The reduction of RWM amplitude led to a reduction of the edge ion temperature disturbances (Fig. 6 shows the case of N 20% above the no-wall limit). Without feedback, the ion temperature fluctuated with T i ~ kev near the edge of the plasma due to Hz ELM events, which excited ELM-driven RWMs of 3 5 Gauss. When the feedback was applied, T i at the top of the H-mode pedestal was reduced to ~0.2 kev as a consequence of the mode amplitude reduction to ~1 Gauss level. FIG. 6. The edge ion temperature disturbances with/without feedback in a discharge with N 20% above the no-wall limit. The statistical variation is shown by overlaying 40 profiles over a time interval of 80 ms. Too-frequent ELM events can cause difficulty for the feedback. The left column of Fig. 7 shows inefficient feedback when feedback with I-coil-only was applied to a high N plasma 20% above the no-wall limit ( N.no-wall estimated ~4l i ). At each ELM event, the feedback, using I-coil currents, tried to reduce the mode amplitude and was successful in holding the GENERAL ATOMICS REPORT GA-A
9 M. Okabayashi, et al. IN DIII-D ADVANCED TOKAMAK PLASMAS amplitude down to ~2 3 Gauss level with modest current (~ a few hundred Amperes) up to t ~ 1550 ms. The requested coil current gradually increased while still sustaining the mode amplitude to a proportionally lower level. However, finally the mode amplitude reached more than 5 Gauss with 1 ka level of coil current, leading to nonlinear stage. A possible process was that this residual RWM grew due to the time-evolving plasma response to a small uncorrected error field. The static error field itself should remain constant on this time scale, ~300 ms, however, the RWM response to the error field could evolve in time. The slow component of I-coil current can be interpreted as the currents needed for suppressing the slowly-time-evolving mode response due to uncorrected error field. FIG. 7. Frequent ELMs resulted in leading to N collapse. (a) Feedback with I-coil-only suppressed the RWM for a few ELMs, however, there was a gradual increase of mode amplitude, which required inefficiently high feedback current. (b) Simultaneous operation with I-coil (fast feedback) and C-coils (slow feedback) reduced the accumulation of RWM amplitude. (a) Plasma rotation at q~2, (b) B p sensor signals (c) I-coil currents, (d) C-coil currents, and (e) D (au). A recipe for better control is to separate the feedback process into two functions: one using internal I-coils for fast ELM-driven RWM control and the other using external C-coils for the slow control of the time-evolving plasma response to the growing residual RWM between ELMs. As shown in the right column of Fig. 7, the two coil set arrangement led to better control. The slow increase of feedback coil currents by C-coil replaced the slow rise in I-coil current. When energizing two feedback systems simultaneously, the I-coil dominantly responded to the ELM events with fast time scale. The difference in the two cases is whether the ELM event took place at finite amplitude of slowly-increasing residual RWM or not. One possible hypothesis is that the formation process of the ELM-driven RWM is affected by the finite amplitude of the residual RWM at the time of ELM events and interferes with the feedback process. Support for this hypothesis was obtained by simulating ELMs with series of n=1 pulses. The use of n=1 pulses is advantageous since the impact is reproducible. The adequacy of simulating ELM with n=1 pulses was confirmed by comparing the decay rates of ELM-driven RWM and the n=1 amplitude excited by n=1 pulses with/without feedback. The response to the applied n=1 pulses was clearly observable [Fig. 8(b,c)], while the amplitude of residual RWM [green shading, Fig. 8(b)] gradually increased. The amplitude and phase of the n=1 plasma response depend on whether the residual RWM exists before the pulse or not as summarized in Fig. 8(d). In particular, the phase shows strong dependence on the residual RWM amplitude. The variation of the n=1 plasma response against the residual RWM is consistent with the hypothesis discussed above Current-driven RWM and Feedback A challenging issue of exploring RWM stabilization in high N plasmas is the nonreproducibility of mode excitation since the high beta RWMs are excited near the operational 6 GENERAL ATOMICS REPORT GA-A26242
10 IN DIII-D ADVANCED TOKAMAK PLASMAS M. Okabayashi, et al. maximum N. Reproducible current driven-rwm at very low beta was extremely useful to investigate the feedback logic. The mode chosen was the current-driven RWM excited at q 95 ~4 by a strong plasma current ramp, whose helical mode structure is fundamentally same as that with the pressure-driven RWM in AT plasmas. FIG. 8. The n=1 pulses (20 ms pulse width) at every 100 ms were used to simulate ELMs. The B p signal shows the gradual increase of residual RWM (green shading) in addition to the response to pulses. (a) The coil currents, (b) B p amplitude, (c) toroidal phase angle, (d) plasma response amplitude and (e) toroidal phase vs the residual RWM level before the pulse applied. Figure 9 shows the feedback performance, where the mode amplitude at the q 95 ~4 was used as a measure of the mode growth. The increase of proportional gain reduced the mode amplitude to ~2 Gauss level and converted a rotational mode to a non-rotational 0 mode. The addition of derivative gain was effective to suppress the mode amplitude. The optimized toroidal phase shift of feedback, FB, was non-zero (shifted degrees in the plasma current direction). Based on the mode response to the derivative gain and the phase shift, it is believed that the RWM feedback functioned as a direct feedback rather than dynamic error field correction against the static error field Mode Non-rigidity Fig. 9. Feedback performance on the current-driven RWM. (a) mode amplitude at q 95 =4 vs proportional gain G p with and without derivative gain G d, (b) mode amplitude vs toroidal phase shift. The feedback functioned as expected in very low N current-drive RWM, but in high N, the operation was found more difficult as discussed in Sec The complexity of feedback operation at high N could be related to more fundamental issues such as mode non-rigidity under the presence of non-axisymmetric field. The mode structure behavior has been studied using the NMA stability code , which predicted that feedback can excite a multitude of stable RWMs that couple to the original unstable RWM. This multiple mode involvement can cause a deformation of the mode structure, including the patterns of eddy currents on both the resistive wall and the plasma during the feedback process. The nonrigidity is substantial when the plasma beta is high and the feedback coils are not well matched to the mode structure [Fig. 10(a,b)]. The effect of non-rigidity is minimized by GENERAL ATOMICS REPORT GA-A
11 M. Okabayashi, et al. IN DIII-D ADVANCED TOKAMAK PLASMAS optimizing the coupling of the feedback coils to the primarily unstable RWM, e.g. by using the I-coils [Fig. 10(c)]. The relevance of this phenomenon to ITER is being studied for various proposed alternative feedback coil configurations. FIG. 10. An example of inefficient feedback configuration with C-coils and improvement with I-coils. Marginal RWM with feedback B p pattern on the vacuum wall. Using external C-coil feedback at high results in large changes to the mode structure. The helicity switches from the left handed helicity of the equilibrium magnetic field to opposite that as varies from (a) just above the no-wall limit to (b) just below the ideal-wall stability limit. (c) Using I-coil feedback, the mode non-rigidity can be greatly reduced even just below the ideal-wall stability limit. 4. Summary At very low plasma rotation, the RWM and NTM have been simultaneously suppressed for durations over 2 s with N above the no-wall limit, with modest power of ECCD. This result strongly indicates possible existence of RWM stabilization mechanisms in addition to the rotational stabilization. Even when the plasma is stabilized, large amplitude RWMs were transiently excited by MHD activity, such as q=2 fishbones and ELMs. The feedback control was found to be effective in several plasma conditions. Fluctuation of the H-mode pedestal due to ELM-driven RWM was reduced with feedback control. The dominant ~0 component of fishbone-driven RWMs was suppressed, although the rotating component suppression remains a future challenge. Simultaneous fast and slow feedback was successful to reduce the onset of N collapse due to the ELM-driven RWM, suggesting that the residual RWM plays a role of hidden parameter. The effectiveness of feedback operation was demonstrated using reproducible current-driven RWM. Using the NMA code, analysis has been carried out to show that better matching of the feedback field pattern to the unstable RWM in high N reduces the mode non-rigidity. The present findings are extremely useful to aid in the challenge of comprehensive control of RWM in the unexplored physics territory of the ignited condition in ITER. This work was supported in part by the US Department of Energy under DE-AC02-76CH03073, DE-FC02-04ER54698, DE-FG02-03ER83657, and DE-FG02-89ER References  TURNBULL, A.D., et al., Phys. Rev. Lett. 74, 718 (1995).  GAROFALO, A., et al., Nucl. Fusion 47, 1121 (2007).  REIMERDES, H., et al., Phys. Rev. Lett. 98, (2007).  TAKECHI, M., et al., Phys. Rev. Lett. 98, (2007).  BUTTERY, R.J., Phys. Plasmas 15, (2008).  BRENNAN, D.P., Phys. Plasmas 9, 2998 (2002).  GAROFALO, A., et al., Phys. Plasmas 13, (2006).  CHU, M.S., et al., Nucl. Fusion 43, 441 (2003).  PRATER, R., Nucl. Fusion 47, 371 (2007).  STRAIT, E.J., et al., Phys. Plasmas 11, 2505 (2004).  HU, Bo., and BETTI, R., Phys. Rev. Lett. 93, (2004).  WESSON, J.A., Plasma Phys. Control. Fusion 37, A337 (1995).  REIMERDES, H., et al., Plasma. Phys. Control. Fusion 49, B349 (2007). 8 GENERAL ATOMICS REPORT GA-A26242
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GA A24014 STABILIZATION OF THE RESISTIVE WALL MODE IN DIII D BY PLASMA ROTATION AND MAGNETIC FEEDBACK by M. Okabayashi, J. Bialek, M.S. Chance, M.S. Chu, E.D. Fredrickson, A.M. Garofalo, R. Hatcher, T.H.
GA A27235 EULERIAN SIMULATIONS OF NEOCLASSICAL FLOWS AND TRANSPORT IN THE TOKAMAK PLASMA EDGE AND OUTER CORE by E.A. BELLI, J.A. BOEDO, J. CANDY, R.H. COHEN, P. COLELLA, M.A. DORF, M.R. DORR, J.A. HITTINGER,
UNDERSTANDING TRANSPORT THROUGH DIMENSIONLESS PARAMETER SCALING EXPERIMENTS by C.C. PETTY and T.C. LUCE JULY 1997 CENERaL ATOMRCS This report was prepared as an account of work sponsored by an agency of
GA A25445 TARGET PLATE CONDITIONS DURING STOCHASTIC BOUNDARY OPERATION ON DIII D by J.G. WATKINS, T.E. EVANS, C.J. LASNIER, R.A. MOYER, and D.L. RUDAKOV JUNE 2006 QTYUIOP DISCLAIMER This report was prepared
Stationary, High Bootstrap Fraction Plasmas in DIII-D Without Inductive Current Control P. A. Politzer, 1 A. W. Hyatt, 1 T. C. Luce, 1 F. W. Perkins, 4 R. Prater, 1 A. D. Turnbull, 1 D. P. Brennan, 5 J.
GA A23977 DETAILED MEASUREMENTS OF ECCD EFFICIENCY ON DIII D by C.C. PETTY, R. PRATER, J. LOHR, T.C. LUCE, R.A. ELLIS, III, R.W. HARVEY, J.E. KINSEY, L.L. LAO, and M.A. MAKOWSKI MAY 2002 DISCLAIMER This
GA A27433 THE EPED PEDESTAL MODEL: EXTENSIONS, APPLICATION TO ELM-SUPPRESSED REGIMES, AND ITER PREDICTIONS by P.B. SNYDER, T.H. OSBORNE, M.N.A. BEURSKENS, K.H. BURRELL, R.J. GROEBNER, J.W. HUGHES, R. MAINGI,
GA A22571 REDUCTION OF TOROIDAL ROTATION BY FAST WAVE POWER IN DIII D by J.S. degrassie, D.R. BAKER, K.H. BURRELL, C.M. GREENFIELD, H. IKEZI, Y.R. LIN-LIU, C.C. PETTY, and R. PRATER APRIL 1997 This report
GA A26686 FAST ION EFFECTS DURING TEST BLANKET MODULE SIMULATION EXPERIMENTS IN DIII-D by G.J. KRAMER, B.V. BUDNY, R. ELLIS, W.W. HEIDBRINK, T. KURKI-SUONIO, R. NAZIKIAN, A. SALMI, M.J. SCHAFFER, K. SHINOHARA,
Analysis and modelling of MHD instabilities in DIII-D plasmas for the ITER mission by F. Turco 1 with J.M. Hanson 1, A.D. Turnbull 2, G.A. Navratil 1, C. Paz-Soldan 2, F. Carpanese 3, C.C. Petty 2, T.C.
Extended Lumped Parameter Model of Resistive Wall Mode and The Effective Self-Inductance M.Okabayashi, M. Chance, M. Chu* and R. Hatcher A. Garofalo**, R. La Haye*, H. Remeirdes**, T. Scoville*, and T.
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GA A25808 DIII D INTEGRATED PLASMA CONTROL SOLUTIONS FOR ITER AND NEXT- GENERATION TOKAMAKS by D.A. HUMPHREYS, J.R. FERRON, A.W. HYATT, R.J. La HAYE, J.A. LEUER, B.G. PENAFLOR, M.L. WALKER, A.S. WELANDER,
in Low Rotation H-modes by Richard Buttery 1 with Rob La Haye 1, Yueqiang Liu 2, Bob Pinsker 1, Jong-kyu Park 3, Holger Reimerdes 4, Ted Strait 1, and the DIII-D research team. 1 General Atomics, USA 2
Plasma Stability in Tokamaks and Stellarators Gerald A. Navratil GCEP Fusion Energy Workshop Princeton, NJ 1- May 006 ACKNOWLEDGEMENTS Borrowed VGs from many colleagues: J. Bialek, A. Garofalo,R. Goldston,
GA A24838 CONTRIBUTIONS FROM THE NEUTRAL BEAMLINE IRON TO PLASMA NON-AXISYMMETRIC FIELDS by J.L. LUXON MARCH 2005 QTYUIOP DISCLAIMER This report was prepared as an account of work sponsored by an agency
GA A24166 SUPER-INTENSE QUASI-NEUTRAL PROTON BEAMS INTERACTING WITH PLASMA: A NUMERICAL INVESTIGATION by H. RUHL, T.E. COWAN, and R.B. STEPHENS OCTOBER 2 DISCLAIMER This report was prepared as an account
Dependence of Achievable β N on Discharge Shape and Edge Safety Factor in DIII D Steady-State Scenario Discharges by J.R. Ferron with T.C. Luce, P.A. Politzer, R. Jayakumar, * and M.R. Wade *Lawrence Livermore
GA A23403 GAS PUFF FUELED H MODE DISCHARGES WITH GOOD ENERGY CONFINEMENT ABOVE THE GREENWALD DENSITY LIMIT ON DIII D by T.H. OSBORNE, M.A. MAHDAVI, M.S. CHU, M.E. FENSTERMACHER, R.J. La HAYE, A.W. LEONARD,
GA A25410 DISRUPTION CHARACTERIZATION AND DATABASE ACTIVITIES FOR ITER by J.C. WESLEY, A.W. HYATT, E.J. STRAIT, D.P. SCHISSEL, S.M. FLANAGAN, T.C. HENDER, Y. GRIBOV, P.C. devries, E.J. FREDRICKSON, D.A.
GA A26123 PARTICLE, HEAT, AND SHEATH POWER TRANSMISSION FACTOR PROFILES DURING ELM SUPPRESSION EXPERIMENTS ON DIII-D by J.G. WATKINS, T.E. EVANS, I. JOSEPH, C.J. LASNIER, R.A. MOYER, D.L. RUDAKOV, O. SCHMITZ,
SciDAC CENTER FOR SIMULATION OF WAVE-PLASMA INTERACTIONS GA A27760 ITERATED FINITE-ORBIT MONTE CARLO SIMULATIONS WITH FULL-WAVE FIELDS FOR MODELING TOKAMAK ICRF WAVE HEATING EXPERIMENTS Final Report for
LLNL-PROC-432803 Scaling of divertor heat flux profile widths in DIII-D C. J. Lasnier, M. A Makowski, J. A. Boedo, S. L. Allen, N. H. Brooks, D. N. Hill, A. W. Leonard, J. G. Watkins, W. P. West May 20,
GA A26741 SCINTILLATOR-BASED DIAGNOSTIC FOR FAST ION LOSS MEASUREMENTS ON DIII-D by R.K. FISHER, D.C. PACE, M. GARCÍA-MUÑOZ, W.W. HEIDBRINK, C.M. MUSCATELLO, M.A. VAN ZEELAND and Y.B. ZHU JUNE 2010 DISCLAIMER
PPPL-3156, Preprint: March 1996, UC-420, 427 Role of Flow Shear in Enhanced Core Confinement Regimes TS Hahm and KH Burrell The importance of the ExB fla shear in arioi s enhanced confinement regimes is
Abstract A database has been developed to study the evolution, the nonlinear effects on equilibria, and the disruptivity of locked and quasi-stationary modes with poloidal and toroidal mode numbers m=2
GA A22689 SLOW LINER FUSION by AUGUST 1997 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any
G A-A22340 PLASMA MASS DENSITY, SPECIES MIX AND FLUCTUATION DIAGNOSTICS USING FAST ALFVEN WAVE by H. IKEZI, J.S. degrassie, R.1. PINSKER, and RET. SNIDER JUNE 1996 GENERAL ATOMICS DISCLAIMER I This report
I-07 Advanced Tokamak Research in and JT-60SA A. Isayama for the JT-60 team 18th International Toki Conference (ITC18) December 9-12, 2008 Ceratopia Toki, Toki Gifu JAPAN Contents Advanced tokamak development
1 EXC/P5-02 ELM Suppression in DIII-D Hybrid Plasmas Using n=3 Resonant Magnetic Perturbations B. Hudson 1, T.E. Evans 2, T.H. Osborne 2, C.C. Petty 2, and P.B. Snyder 2 1 Oak Ridge Institute for Science
OV/-5 Overview of Recent Experimental Results From the DIII D Advanced Tokamak Program K.H. Burrell for the DIII D Team General Atomics, P.O. Box 8568, San Diego, California 986-568 email: email@example.com
1 EX/P8-07 Global Mode Control and Stabilization for Disruption Avoidance in High-β NSTX Plasmas * J.W. Berkery 1, S.A. Sabbagh 1, A. Balbaky 1, R.E. Bell 2, R. Betti 3, J.M. Bialek 1, A. Diallo 2, D.A.
Response of a Resistive and Rotating Tokamak to External Magnetic Perturbations Below the Alfven Freuency by M.S. Chu In collaboration with L.L. Lao, M.J. Schaffer, T.E. Evans E.J. Strait (General Atomics)
GA A26891 A FIRST PRINCIPLES PREDICTIVE MODEL OF THE PEDESTAL HEIGHT AND WIDTH: DEVELOPMENT, TESTING, AND ITER OPTIMIZATION WITH THE EPED MODEL by P.B. SNYDER, R.J. GROEBNER, J.W. HUGHES, T.H. OSBORNE,
UNDERSTANDING AND CONTROL OF TRANSPORT IN ADVANCED TOKAMAK REGIMES IN Presented by C.M. GREENFIELD for J.C. DeBOO, T.C. LUCE, B.W. STALLARD, E.J. SYNAKOWSKI, L.R. BAYLOR,3 K.H. BURRELL, T.A. CASPER, E.J.
GA A22993 EFFECTS OF PLASMA SHAPE AND PROFILES ON EDGE by L.L. LAO, V.S. CHAN, L. CHEN, E.J. DOYLE, J.R. FERRON, R.J. GROEBNER, G.L. JACKSON, R.J. LA HAYE, E.A. LAZARUS, G.R. McKEE, R.L. MILLER, M. MURAKAMI,
GA A26116 THE CONCEPTUAL MODEL OF THE MAGNETIC TOPOLOGY AND NONLINEAR DYNAMICS OF ELMs by T.E. EVANS, J.H. YU, M. JAKUBOWSKI, O. SCHMITZ, J.G. WATKINS, and R.A. MOYER JUNE 2008 DISCLAIMER This report was
Effects of Noise in Time Dependent RWM Feedback Simulations O. Katsuro-Hopkins, J. Bialek, G. Navratil (Department of Applied Physics and Applied Mathematics, Columbia University, New York, NY USA) Building
HIGH PERFORMANCE EXPERIMENTS IN JT-U REVERSED SHEAR DISCHARGES IAEA-CN-9/EX/ T. FUJITA, Y. KAMADA, S. ISHIDA, Y. NEYATANI, T. OIKAWA, S. IDE, S. TAKEJI, Y. KOIDE, A. ISAYAMA, T. FUKUDA, T. HATAE, Y. ISHII,
PROGRESS IN STEADY-STATE SCENARIO DEVELOPMENT IN THE DIII-D TOKAMAK by T.C. LUCE, J.R. FERRON, C.T. HOLCOMB, F. TURCO, P.A. POLITZER, and T.W. PETRIE GA A26981 JANUARY 2011 DISCLAIMER This report was prepared
Research in Support of ITER by E.J. Strait and the Team Presented at 22nd IAEA Fusion Energy Conference Geneva, Switzerland October 13-18, 28 DIII-D Research Has Made Significant Contributions in the Design
GA A22636 RECENT H MODE DENSITY LIMIT EXPERIMENTS ON DIII D by M.A. MAHDAVI, R. MAINGI, R.J. LA HAYE, T.C. JERNIGAN, T.W. PETRIE, L.R. BAYLOR, A.W. HYATT, A.W. LEONARD, M. MURAKAMI, L.W. OWENS, R.T. SNIDER,
GA A22877 A NEW DC MAGNETIC SENSOR by JUNE 1998 DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor
UCRL-JC- 134707 PREPRINT Impurity Transport Studies of Intrinsic MO and Injected Ge in High Temperature ECRH Heated FTU Tokamak Plasmas D. Pacella, M. May KB. Fournier, M. Finkenthal M. Mattioli, M. Zerbini
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PHYSICS OF PLASMAS 14, 022505 2007 Effect of an error field on the stability of the resistive wall mode Richard Fitzpatrick Institute for Fusion Studies, Department of Physics, University of Texas at Austin,
MHD instability driven by supra-thermal electrons in TJ-II stellarator K. Nagaoka 1, S. Yamamoto 2, S. Ohshima 2, E. Ascasíbar 3, R. Jiménez-Gómez 3, C. Hidalgo 3, M.A. Pedrosa 3, M. Ochando 3, A.V. Melnikov
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MHD Analysis of the Tokamak Edge Pedestal in the Low Collisionality Regime Thoughts on the Physics of ELM-free QH and RMP Discharges P.B. Snyder 1 Contributions from: H.R. Wilson 2, D.P. Brennan 1, K.H.
1 EX/P6-29 Observation of Neo-Classical Ion Pinch in the Electric Tokamak* R. J. Taylor, T. A. Carter, J.-L. Gauvreau, P.-A. Gourdain, A. Grossman, D. J. LaFonteese, D. C. Pace, L. W. Schmitz, A. E. White,
GA A677 THERMAL ANALYSIS AND TESTING FOR DIII D OHMIC HEATING COIL by C.B. BAXI, P.M. ANDERSON, and A.M. GOOTGELD NOVEMBER 1997 DISCLAIMER This report was prepared as an account of work sponsored by an
GA A25580 EVIDENCE FOR ANOMALOUS EFFECTS ON THE CURRENT EVOLUTION IN TOKAMAK OPERATING SCENARIOS by T.A. CASPER, R.J. JAYAKUMAR, S.L. ALLEN, C.T. HOLCOMB, M.A. MAKOWSKI, L.D. PEARLSTEIN, H.L. BERK, C.M.