DIII-D RESEARCH OPPORTUNITIES FORUM FOR THE 2014 EXPERIMENTAL CAMPAIGN
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(Proposal numbers 1-382 are from 2013) | |||||||||
ID | Title | Research Area | Name | Affiliation |
Time Req'ed |
ITPA Joint Exp |
ITER IO Urgent Research Task |
||
24 | Plasma response to 3D magnetic perturbations in the unfavorable grad-B drift direction | ELM Control | PPPL | Yes | No | No | |||
37 | Identification of I-mode through simultaneous core and edge turbulence measurements | Turbulence & Transport | Massachusetts Institute of Technology | Yes | No | No | |||
50 | Improved Heat Load Reduction Using Long Outer Divertor Leg Geometry During Puff and Pump Operation | Divertor & SOL Physics | GA | Yes | No | No | |||
57 | Develop a high performance L-mode plasma. | General Physics | ORNL | Yes | No | No | |||
58 | Progressing Towards a Staged Approach to Disruption Mitigation | Disruption Mitigation | GA | Yes | No | Yes | |||
61 | Energy Transport During Electron-Dominated Heating of ITER-Relevant H-Mode Discharges | Inductive Scenarios | PPPL | Yes | No | No | |||
62 | RMP assisted snowflake divertor | Divertor & SOL Physics | U of Wisconsin | Yes | No | No | |||
66 | 13C-methane injection into USN re C migration to walls and ITER decision about PFC target material | Plasma-material Interface | U of Toronto | Yes | Yes | Yes | |||
70 | DIMES test of misaligned CFC tile to establish size of misalignment needed to disrupt ITER | Plasma-material Interface | U of Toronto | Yes | No | No | |||
72 | Energy Transport During Electron-Dominated Heating of ITER-Relevant H-Mode Discharges | Turbulence & Transport | PPPL | Yes | No | No | |||
73 | Test optimized TBM error field correction at higher values of beta | Stability & Disruption Avoidance | CRPP-EPFL | Yes | No | No | |||
74 | Optimize TBM error field correction against field penetration in low NBI torque H-modes | Stability & Disruption Avoidance | CRPP-EPFL | Yes | No | No | |||
75 | Evaluate the potential of correcting more than one mode component of the TBM error field | Stability & Disruption Avoidance | CRPP-EPFL | Yes | No | No | |||
76 | Connection between particle and momentum transport | Turbulence & Transport | The college of William and Mary | Yes | Yes | Yes | |||
77 | Influence of rotation and rotation shear on ELM suppression | ELM Control | The college of William and Mary | Yes | No | No | |||
78 | 3D magnetics plasma response measurements of n=1 perturbations for RWM analysis & model validation | Stability & Disruption Avoidance | Department of Energy | Yes | No | Yes | |||
79 | 3D magnetics equilibrium measurements to applied n=3 perturbations | Stability & Disruption Avoidance | Department of Energy | Yes | No | Yes | |||
80 | Poloidal spectral measurements of n=3 RMP ELM suppression using the 3D magnetics upgrade | ELM Control | Department of Energy | Yes | No | Yes | |||
83 | Establishing stationary I-mode with high performance | ELM Control | Massachusetts Institute of Technology | Yes | Yes | No | |||
84 | Influence of resonant/non-resonant magnetic perturbation on particle confinement with n=2 | ELM Control | Max-Planck Institute for Plasma Physics | Yes | Yes | No | |||
85 | Current profile control for stable ITER baseline scenario plasmas | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |||
87 | farSOL expts at high n/nGW to establish if ITER farSOL will be high-recycling/detached | Divertor & SOL Physics | U of Toronto | Yes | No | Yes | |||
88 | inner column limiter expts to establish if ITER wall-limiter design should include �??funnel effect' | Divertor & SOL Physics | U of Toronto | Yes | No | Yes | |||
89 | Mo, W, Al, Be DiMES net/gross erosion experiments | Plasma-material Interface | U of Toronto | Yes | Yes | Yes | |||
91 | Complete the Development of PCS n=2 Error Field Control Algorithm | Stability & Disruption Avoidance | Department of Energy | Yes | No | No | |||
92 | H-mode Optimization of n=1&2 Error Field Control Currents | Stability & Disruption Avoidance | Department of Energy | Yes | No | No | |||
93 | Active Control of the EHO in Quiescent H-modes | Plasma Control | Department of Energy | Yes | No | No | |||
97 | Time-resolved measurement of plasma response spectrum | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |||
98 | Develop feedback-controlled MHD spectroscopy | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |||
99 | Understand and control resistive wall mode stability in high-qmin plasmas | Stability & Disruption Avoidance | Columbia U | Yes | Yes | No | |||
100 | Understand resistive wall mode control physics in low-q95 plasmas | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |||
101 | Investigation of n=1 RMP effects on ELMs with pitch-aligned configuration of I-coils | ELM Control | PPPL | Yes | Yes | Yes | |||
102 | TBM mock-up effects on confinement at high β | Stability & Disruption Avoidance | ITER Organization | Yes | No | Yes | |||
103 | Probing and controlling the L->H and H->L transitions by small pellet injection | L-H Transition | Korea Institute of Fusion Energy | Yes | No | No | |||
104 | Comparision of small-ELM regimes in DIII-D and NSTX | ELM Control | U of Wisconsin | Yes | No | No | |||
105 | Optimization and exploration of the q95<2 scenario in DIII-D | Stability & Disruption Avoidance | Consorzio RFX | Yes | No | No | |||
106 | Magnetic turbulence measurements in high beta H-mode discharges | Turbulence & Transport | PPPL | Yes | No | No | |||
107 | Error field detection by application of a "spiraling" error field | Stability & Disruption Avoidance | ORNL | Yes | No | No | |||
108 | Disruption avoidance by forced magnetic spin-up of NTMs | Stability & Disruption Avoidance | ORNL | Yes | No | No | |||
109 | Electron Heat Transport in E-Dominated Heating of ITER-like H-Mode Discharges with Modulated ECH | Inductive Scenarios | U of Wisconsin | Yes | No | No | |||
110 | Electron Heat Transport in E-Dominated Heating of ITER-like H-Mode Discharges with Modulated ECH | Turbulence & Transport | U of Wisconsin | Yes | No | No | |||
111 | Dependence of I-mode on current direction and heating mix | ELM Control | Massachusetts Institute of Technology | Yes | Yes | No | |||
112 | 2D imaging of small ELMs | ELM Control | Los Alamos National Laboratory | Yes | No | No | |||
113 | Heat Load during slow current quench phase of disruptions/VDEs and its relation with poloidal halo c | Disruption Mitigation | ITER Organization | Yes | No | Yes | |||
114 | Toroidal peaking of radiation, response time for triggering TQ and mitigation efficiency during mass | Disruption Mitigation | ITER Organization | Yes | No | Yes | |||
116 | Influence of non-axisymmetric fields (TBMs / RMPs) on fast ion confinement and loss | Energetic Particles | ITER Organization | Yes | Yes | Yes | |||
117 | Conditions for nonlinear Alfvén Eigenmode evolution and impact on fast ion confinement and loss | Energetic Particles | ITER Organization | Yes | Yes | Yes | |||
118 | Dominant electron heated ITER baseline scenario studies | Inductive Scenarios | Columbia U | Yes | No | No | |||
119 | Impact of fast-ions on the RWM stability boundary | Stability & Disruption Avoidance | Columbia U | Yes | Yes | No | |||
121 | Testing Emerging Two-Fluid Model for RMP Plasma Response in Straightforward IWL Plasmas | ELM Control | ORNL | Yes | No | No | |||
122 | Bid farewell to locked modes - NTM-locking avoidance by feedback synchronization assisted with ECCD | Stability & Disruption Avoidance | PPPL | Yes | No | No | |||
126 | Triggering ELMs at high frequency with PPPL Lithium granule injector | ELM Control | Retired from PPPL | Yes | No | No | |||
127 | Characterization of Intense Bursts of Millimeter Wave Emission in QH-mode Plasma | Inductive Scenarios | UC, Davis | Yes | No | No | |||
129 | Optimization and Control of ITER-like MGI | Disruption Mitigation | GA | Yes | Yes | Yes | |||
131 | Understanding runaway equilibrium to minimize damage hazard | Disruption Mitigation | Yes | Yes | Yes | ||||
133 | Fast Runaway Shutdowns by MGI | Disruption Mitigation | GA | Yes | Yes | Yes | |||
134 | Pedestal stability and divertor transport studies with feedback-controlled snowflake configuration. | Divertor & SOL Physics | LLNL | Yes | No | No | |||
137 | 3D material migration during RMP ELM suppression | ELM Control | U of Wisconsin | Yes | Yes | Yes | |||
142 | ELM heat transport in the snowflake divertor. | Divertor & SOL Physics | LLNL | Yes | No | No | |||
143 | RMP ELM control at low torque | ELM Control | UCSD | Yes | No | No | |||
144 | Validation of kink response models with rotating n = 1 and n = 2 and phase flip n = 3 RMPs | ELM Control | UCSD | Yes | No | No | |||
146 | ELM suppression with Saturated walls | ELM Control | UCSD | Yes | No | No | |||
147 | Natural and Pellet-induced ELM behavior at low rotation/torque | ELM Control | UCSD | Yes | No | No | |||
148 | Radiative divertor control development | Divertor & SOL Physics | LLNL | Yes | No | No | |||
153 | Controlling VH-mode with RMPs and comparison to NSTX EPH-mode | ELM Control | ORNL | Yes | No | No | |||
156 | Controlling the timing and evolution of L-H and H-L with 3D fields | Plasma Control | PPPL | Yes | No | No | |||
159 | Collisionality dependence of pedestal height with RMP | Pedestal Structure | GA | Yes | No | No | |||
163 | Exploration of DEFC in the feedback stabilized plasma in low-q discharges | Stability & Disruption Avoidance | PPPL | Yes | No | No | |||
177 | Possibility of â??Off-axis-Fishbone Mode and ELM Pacingâ?? due to Direct Energetic Particle Coupling | ELM Control | PPPL | Yes | No | No | |||
183 | Measurement of multiple mechanisms in the low-density limit via ellipticity in the compass scan | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |||
185 | Measure Plasma Response to RMPs | ELM Control | GA | Yes | No | No | |||
186 | Optimal Mixing of I & C coils for n=1 EFC | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |||
187 | H-mode 3-D field optimization with purely kink-resonant and non-resonant n=1 fields | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |||
191 | Critical electric field for runaway electron growth and decay under quiescent conditions | Disruption Mitigation | Columbia U | Yes | Yes | No | |||
193 | Magnetic perturbation amplitude scan to investigate RMP-induced damping of Zonal Flows | Turbulence & Transport | U of Wisconsin | Yes | No | No | |||
196 | Narrow heat flux widths and divertor power dissipation | Divertor & SOL Physics | GA | Yes | Yes | Yes | |||
197 | Scaling of divertor detachment onset | Divertor & SOL Physics | GA | Yes | No | No | |||
198 | Compare the power threshold for pre-emptive NTM suppression vs Catch and Subdue | Stability & Disruption Avoidance | PPPL | Yes | No | No | |||
199 | Reducing the tearing island detection time | Stability & Disruption Avoidance | PPPL | Yes | No | No | |||
200 | Multiple periods of NTM suppression | Stability & Disruption Avoidance | PPPL | Yes | No | No | |||
201 | NTM Control Upgrade: Capibility to deposit EC at multiple locations | Plasma Control | PPPL | Yes | No | No | |||
202 | Error Field Correction Improvement: Adding BetaN dependence | Stability & Disruption Avoidance | PPPL | Yes | No | No | |||
203 | Dynamic plasma-wall equilibrium in ELMy H-mode | Divertor & SOL Physics | CompX | Yes | No | No | |||
208 | qmin control | Steady State Heating and Current Drive | PPPL | Yes | No | No | |||
209 | RMP ELM-Control for Snowflake Configurations | Torkil Jensen Award | LLNL | Yes | No | No | |||
211 | Control of experimentally simulated burning state | Plasma Control | QST | Yes | No | No | |||
212 | Island seeding with saw teeth pacing: New method to control tearing modes | Stability & Disruption Avoidance | PPPL | Yes | No | No | |||
213 | Real-time Ray Tracing for PCS | Plasma Control | PPPL | Yes | No | No | |||
214 | Density (Greenwald) Limit and the Radiation Driven Islands | Torkil Jensen Award | PPPL | Yes | No | No | |||
216 | Campaign to study physics at the Greenwald limit | Steady State Heating and Current Drive | PPPL | Yes | No | No | |||
217 | PID (proportional integral derivative)control of Error Field | Stability & Disruption Avoidance | PPPL | Yes | No | No | |||
218 | Controlled Snowflake Divertor Study | Divertor & SOL Physics | PPPL | Yes | No | No | |||
221 | Gas Injection Feedback with Radiation Measurements | Divertor & SOL Physics | PPPL | Yes | No | No | |||
222 | Investigation of optimum pellet injection geometry for pellet triggering minimum throughput/PFC flux | ELM Control | ITER Organization | Yes | No | Yes | |||
223 | Demonstration of integrated ELM-paced pellet fuelled H-mode plasma in ITER-relevant range. | ELM Control | ITER Organization | Yes | Yes | Yes | |||
224 | Determination of minimum confinement degradation for ELM suppression with I coils | ELM Control | ITER Organization | Yes | No | Yes | |||
225 | Study of atomic and molecular processes in deep detachment conditions | Divertor & SOL Physics | LLNL | Yes | No | No | |||
226 | Compatibility of ELM suppressed regimes by 3-D fields with pellet injection for plasma fuelling | ELM Control | ITER Organization | Yes | No | Yes | |||
227 | Mechanisms leading to termination of the runaway discharges and effects on PFC energy deposition | Disruption Mitigation | ITER Organization | Yes | No | Yes | |||
228 | High resolution study of collisionality and target structure in the transition to full detachment | Divertor & SOL Physics | LLNL | Yes | No | No | |||
229 | CQ de-confinement of REs using pulsed impurity injection | Disruption Mitigation | ITER Organization | Yes | No | Yes | |||
230 | Assessment of the degree of detachment using NIR spectroscopy | Divertor & SOL Physics | LLNL | Yes | No | No | |||
232 | Bifurcated helical core equilibrium - continued | Stability & Disruption Avoidance | U of Wisconsin | Yes | No | No | |||
237 | Critical electric field for runaway electron growth and decay under quiescent conditions | Disruption Mitigation | Massachusetts Institute of Technology | Yes | Yes | No | |||
238 | Direct Measurement of NTV Torque | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |||
239 | Continuous Scan of NTV Torque Across Low Rotation Peak | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |||
240 | Optimization of Applied Error Field Spectrum for NTV | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |||
255 | Super H-Mode | Torkil Jensen Award | ORNL | Yes | No | No | |||
270 | L-mode Turbulence and L-H Transition Characterization in Snowflake Divertor Plasmas | Divertor & SOL Physics | LLNL | Yes | No | No | |||
271 | Investigation of Momentum transport with Modulated ECH and ECH resonance layer sweeping | Plasma Rotation | National Fusion Research Institute (NFRI), Korea | Yes | Yes | Yes | |||
272 | Dither injection for closed-loop system identification of vacuum and plasma response | Torkil Jensen Award | KTH | Yes | No | No | |||
273 | Sawtooth control via n=1 external magnetic perturbation | Torkil Jensen Award | Consorzio RFX and Padova U | Yes | No | No | |||
274 | Investigation of Momentum transport with Modulated ECH and ECH resonance layer sweeping | Plasma Rotation | National Fusion Research Institute | Yes | Yes | Yes | |||
275 | Investigation of Momentum transport with Modulated ECH and ECH resonance layer sweeping | Plasma Rotation | National Fusion Research Institute | Yes | Yes | Yes | |||
276 | Investigation of Momentum transport with power ratio P_ECH/P_NBI and torque ratio scan | Plasma Rotation | National Institute for Fusion Science, Toki, Japan | Yes | Yes | Yes | |||
277 | ECH effects on low or balanced torque discharges in DIII-D | Plasma Rotation | National Fusion Research Institute (NFRI), Korea | Yes | Yes | No | |||
279 | ECH effects on low or balanced torque discharges in DIII-D | Plasma Rotation | National Fusion Research Institute (NFRI), Korea | Yes | Yes | No | |||
281 | ECH effects on low or balanced torque discharges in DIII-D | Plasma Rotation | National Fusion Research Institute (NFRI), Korea | Yes | Yes | No | |||
282 | Investigation of Momentum transport with power ratio PECH/PNBI and torque ratio Ï?NBI/ PECH scan | Plasma Rotation | National Institute for Fusion Science, Toki, Japan | Yes | Yes | Yes | |||
296 | Determine dependence of RWM marginal stability on rotation and energetic particles | Stability & Disruption Avoidance | Columbia U | Yes | Yes | Yes | |||
301 | Access to the small ELM regime with a shape control | ELM Control | ORNL | Yes | No | No | |||
341 | Investigation of Momentum Transport with Power ratio PECH/PNBI and torque ratio Ï?NBI/PECH scan | Plasma Rotation | National Institute for Fusion Science, Toki, Japan | Yes | Yes | Yes | |||
358 | Investigation of Momentum transport with Modulated ECH and ECH resonance layer scan | Plasma Rotation | National Fusion Research Institute | Yes | Yes | Yes | |||
421 | Investigate Disagreements Between Thomson Scattering and ECE Measurements in High Te Discharges | General Physics | Massachusetts Institute of Technology | Yes | Yes | No | |||
423 | Coupling of multi-channel transport and turbulence across rotation reversals | Plasma Rotation | Massachusetts Institute of Technology | Yes | Yes | No | |||
424 | Search for evidence of non-local transport across slow L-H transitions | Turbulence & Transport | Massachusetts Institute of Technology | Yes | No | No | |||
425 | Flow or flow shear for m/n=2/1 tearing mode stabilization? | Stability & Disruption Avoidance | Retired from GA | Yes | Yes | No | |||
436 | High Beta Hybrids and Pressure Profile Broadening | Steady State Heating and Current Drive | GA | Yes | No | No | |||
446 | Probe the viscosity of inter-mode coupling | Plasma Rotation | Los Alamos National Laboratory | Yes | No | No | |||
447 | Confinement and stability properties of 'resonant' MHD rotation | Plasma Rotation | Los Alamos National Laboratory | Yes | No | No | |||
449 | Drift wave and NTM coupling | Turbulence & Transport | Los Alamos National Laboratory | Yes | No | No | |||
451 | Disruption mitigation by differential rotation of internal MHD | Stability & Disruption Avoidance | Los Alamos National Laboratory | Yes | No | No | |||
455 | TBM mock-up effects on confinement at high β | Stability & Disruption Avoidance | ITER Organization | Yes | No | Yes | |||
462 | Perturbation amplitude linearity test of the RMP ELM suppression 3D plasma response | ELM Control | Department of Energy | Yes | No | Yes | |||
463 | Exploring collisionality impact on the 3D plasma response during RMP ELM Suppression | ELM Control | Department of Energy | Yes | No | Yes | |||
464 | ITER relevant 3D plasma response variations with respect to BetaN for RMP ELM suppression | ELM Control | Department of Energy | Yes | No | Yes | |||
465 | Explaining the q95 resonant nature of RMP ELM suppression through 3D plasma response measurement | ELM Control | Department of Energy | Yes | No | Yes | |||
466 | Extending hybrid discharges to low noninductive fraction through flux-pumping control | Inductive Scenarios | Department of Energy | Yes | No | No | |||
467 | Sustainment of q<2 through pseudo wall rotation | Inductive Scenarios | Department of Energy | Yes | No | No | |||
468 | H-mode access to q95<2 through 3/2 sustainment and 2/1 preemption | Inductive Scenarios | Department of Energy | Yes | No | No | |||
469 | Experimental guidance for the development of a predictive model of the plasma response to an RMP | ELM Control | PPPL | Yes | No | No | |||
470 | Development of Fully Noninductive High Beta EAST Scenario | Steady State Heating and Current Drive | ASIPP | Yes | No | No | |||
471 | The experiment on generalized hybrid scenario with qmin > 2 at low density and relatively high q95 | Inductive Scenarios | ASIPP | Yes | No | No | |||
472 | Effect of divertor geometry & heating scheme on the characteristic widths of heat flux footprint | Divertor & SOL Physics | ASIPP | Yes | No | No | |||
473 | RMP assisted snowflake divertor | Divertor & SOL Physics | U of Wisconsin | Yes | No | No | |||
474 | 3D material migration during RMP ELM suppression | Plasma-material Interface | U of Wisconsin | Yes | Yes | No | |||
475 | Helium exhaust with 3D fields | ELM Control | U of Wisconsin | Yes | No | No | |||
476 | Impact of TBM-induced field ripple in low-torque ITER baseline | Inductive Scenarios | Department of Energy | Yes | No | Yes | |||
477 | Establishing MHD mode rotation control with EM torque and better understanding of disruptive process | Stability & Disruption Avoidance | PPPL | Yes | No | Yes | |||
478 | Reduction of thermal disruption due to 2/1 mode in q >1 configuration | Stability & Disruption Avoidance | PPPL | Yes | No | Yes | |||
479 | Major disruption avoidance by providing â??magnetic helical insulationâ?? between ST and 2/1 surface | Stability & Disruption Avoidance | PPPL | Yes | No | Yes | |||
480 | Orderly shutdown enhancement of multi-mega joule magnetic energy during the plasma current shut down | Stability & Disruption Avoidance | PPPL | Yes | No | Yes | |||
481 | Spin-up the NTM mode frequency for suppression of NTM by explicitly the EM torque control | Stability & Disruption Avoidance | PPPL | Yes | No | Yes | |||
482 | Disruption study by increasing up to 1kHz of 3/2 (n=2) mode over internally shielded regime | Stability & Disruption Avoidance | PPPL | Yes | No | Yes | |||
483 | Avoidance of NTM mode rotation frequency near the dangerous mechanical resonance | Stability & Disruption Avoidance | PPPL | Yes | No | Yes | |||
484 | Mitigation: Reduction of toroidal-asymmetry of radiation loss by 3D-magnetic mode rotation control | Stability & Disruption Avoidance | PPPL | Yes | No | Yes | |||
485 | Avoidance of NTM mode rotation frequency near the dangerous mechanical resonance | Stability & Disruption Avoidance | PPPL | Yes | No | Yes | |||
486 | Mitigation: pellet and massive gas injections in helically favorable ways for reducing asymmetry | Stability & Disruption Avoidance | PPPL | Yes | No | Yes | |||
487 | Reduction of required power of ECCD NTM suppression targeting in slowly moving x- and o- point | Stability & Disruption Avoidance | PPPL | Yes | No | Yes | |||
498 | Validation of single-mode model of error field correction for n=2 fields | Stability & Disruption Avoidance | Department of Energy | Yes | Yes | No | |||
500 | q95<2 tokamak operation via dynamic error field correction | Stability & Disruption Avoidance | Consorzio RFX | Yes | No | No | |||
503 | Validation of M3D nonlinear MHD simulations of ELMs | Pedestal Structure | UCSD | Yes | No | No | |||
504 | Evolution of mitigation to suppression in RMP H-modes and Validation of nonlinear M3D simulations | ELM Control | UCSD | Yes | No | No | |||
506 | Understanding the synchrotron emission patterns in QRE discharges | Disruption Mitigation | UCSD | Yes | No | No | |||
514 | LOC/SOC Studies | Turbulence & Transport | MIT PSFC | Yes | Yes | No | |||
515 | Inner Wall Limiter experiments in support of ITER limiter design and operation for startup, rampdown | Divertor & SOL Physics | U of Toronto | Yes | No | Yes | |||
516 | DiMES studies of W, Mo and Al gross and net erosion, material migration to benchmark impurity codes | Plasma-material Interface | U of Toronto | Yes | No | Yes | |||
517 | Physics of Crescent-shaped synchrotron emission patterns in runaway plateau dischar | Disruption Mitigation | UCSD | Yes | No | No | |||
520 | Effect of 3-D fields on divertor detachment | Divertor & SOL Physics | ORNL | Yes | No | No | |||
537 | Super H-Mode: Pedestal Evolution and Optimization | Pedestal Structure | ORNL | Yes | No | No | |||
543 | Control of high-Z PFC erosion by local gas injection | Plasma-material Interface | UCSD | Yes | No | No | |||
544 | Super H-Mode: Scenario Development | Steady State Heating and Current Drive | ORNL | Yes | No | No | |||
547 | Induced L-H-L transitions in IWL plasmas with applied n=1 C-coil | L-H Transition | PPPL | Yes | No | No | |||
549 | Testing kinetic RWM stabilization theory at marginal stability in high beta, TM stabilized plasmas | Stability & Disruption Avoidance | Columbia U | Yes | Yes | Yes | |||
557 | Density (Greenwald) Limit and the Radiation Driven Islands | Torkil Jensen Award | PPPL | Yes | No | No | |||
558 | Expand the high li, betaN >4 operating regime through NTM Stabilization and Large Sawtooth Avoidance | Steady State Heating and Current Drive | PPPL | Yes | No | No | |||
562 | RMP NTM interaction | Stability & Disruption Avoidance | PPPL | Yes | No | No | |||
564 | Simulated of Burn Control using In-Vessel Coils | Turbulence & Transport | PPPL | Yes | No | No | |||
569 | High Beta, Steady State Hybrids | Steady State Heating and Current Drive | GA | Yes | No | No | |||
570 | Space, time and energy-resolved x-ray measurements for magnetically confined fusion plasmas | Stability & Disruption Avoidance | PPPL | Yes | No | No | |||
571 | Optimal Plasma Shape for High-Beta, Steady-State Hybrid Scenario | Steady State Heating and Current Drive | GA | Yes | No | No | |||
572 | Collisionality Scaling of High-Beta, Steady-State Hybrids | Steady State Heating and Current Drive | GA | Yes | No | No | |||
574 | Influence of non-axisymmetric fields (TBMs / RMPs) on fast ion confinement and loss | Energetic Particles | ITER Organization | Yes | No | Yes | |||
575 | Magnetic field limit for Glow Discharge wall cleaning | Plasma Control | ITER Organization | Yes | No | Yes | |||
578 | Â N=2 mode rotation technique development using the current-driven loq q RWM onset | Stability & Disruption Avoidance | PPPL | Yes | No | Yes | |||
581 | Heat flux distribution during major disruptions | Stability & Disruption Avoidance | ITER Organization | Yes | Yes | Yes | |||
582 | Energy deposition during runaway electron impact | Stability & Disruption Avoidance | ITER Organization | Yes | Yes | Yes | |||
583 | Dissipation of runaway energy by high-Z impurity injection | Disruption Mitigation | ITER Organization | Yes | Yes | Yes | |||
584 | n=1 RMP Suppression and the role of field penetration vs kink excitation | ELM Control | GA | Yes | No | No | |||
585 | Compatibility of ELM suppressed regimes by 3-D fields with pellet injection for plasma fuelling | ELM Control | ITER Organization | Yes | No | Yes | |||
586 | Investigation of optimum pellet injection geometry for pellet triggering minimum throughput/PFC flux | ELM Control | ITER Organization | Yes | No | Yes | |||
587 | Demonstration of integrated ELM-paced pellet fuelled H-mode plasma in ITER-relevant range. | ELM Control | ITER Organization | Yes | Yes | Yes | |||
591 | Optimization of edge particle transport in ELM suppressed H-modes including high Z impurity control | ELM Control | ITER Organization | Yes | No | Yes | |||
592 | ECH Control of Alfven Eigenmodes | Energetic Particles | ITER Organization | Yes | Yes | Yes | |||
602 | Rotating field current drive for NTM suppression | Stability & Disruption Avoidance | Massachusetts Institute of Technology | Yes | No | No | |||
616 | Validation of nonlinear models of ELMs and RMP ELM mitigation | ELM Control | Massachusetts Institute of Technology | Yes | No | No | |||
622 | Identification of entrainment threshold in I-coil amplitude/frequency space | Stability & Disruption Avoidance | Massachusetts Institute of Technology | Yes | No | No | |||
626 | Validation of ECCD NTM stabilization criteria | Stability & Disruption Avoidance | ITER Organization | Yes | No | Yes | |||
627 | Core edge integration for QH-mode plasmas in ITER | Divertor & SOL Physics | ITER Organization | Yes | No | Yes | |||
628 | He H-mode plasmas studies for the ITER non-active operational phase | Inductive Scenarios | ITER Organization | Yes | No | Yes | |||
629 | Transport study using Modulation RMP (M-RMP) | ELM Control | Zhejiang U | Yes | No | No | |||
630 | Sawtooth control via n=1 external magnetic perturbation: extension to H-mode plasmas | Stability & Disruption Avoidance | Consorzio RFX | Yes | No | No | |||
631 | Optimization of RMP pedestal with feedback control | ELM Control | GA | Yes | No | Yes | |||
632 | Mutual alignment of gyrotrons: a new technique based on mirror-steering and anti-phase modulation | Steady State Heating and Current Drive | Columbia U | Yes | No | No | |||
633 | Plasma response to small applied rotating fields as an error-field-detection method | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |||
656 | Validating Critical Gradient Model for Burning Plasmas | Energetic Particles | PPPL | Yes | No | No |