DIII-D RESEARCH OPPORTUNITIES FORUM FOR THE 2013 EXPERIMENTAL CAMPAIGN
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| ID | Title | Research Area | Name | Affiliation | 
Time Req'ed  | 
ITPA Joint Exp  | 
ITER IO Urgent Research Task  | 
 
| 24 details | Plasma response to 3D magnetic perturbations in the unfavorable grad-B drift direction | ELM Control | PPPL | Yes | No | No | |
| 37 details | Identification of I-mode through simultaneous core and edge turbulence measurements | Turbulence & Transport | Massachusetts Institute of Technology | Yes | No | No | |
| 50 details | Improved Heat Load Reduction Using Long Outer Divertor Leg Geometry During Puff and Pump Operation | Divertor & SOL Physics | GA | Yes | No | No | |
| 57 details | Develop a high performance L-mode plasma. | General Physics | ORNL | Yes | No | No | |
| 58 details | Progressing Towards a Staged Approach to Disruption Mitigation | Disruption Mitigation | GA | Yes | No | Yes | |
| 61 details | Energy Transport During Electron-Dominated Heating of ITER-Relevant H-Mode Discharges | Inductive Scenarios | PPPL | Yes | No | No | |
| 62 details | RMP assisted snowflake divertor | Divertor & SOL Physics | U of Wisconsin | Yes | No | No | |
| 66 details | 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 details | 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 details | Energy Transport During Electron-Dominated Heating of ITER-Relevant H-Mode Discharges | Turbulence & Transport | PPPL | Yes | No | No | |
| 73 details | Test optimized TBM error field correction at higher values of beta | Stability & Disruption Avoidance | CRPP-EPFL | Yes | No | No | |
| 74 details | Optimize TBM error field correction against field penetration in low NBI torque H-modes | Stability & Disruption Avoidance | CRPP-EPFL | Yes | No | No | |
| 75 details | Evaluate the potential of correcting more than one mode component of the TBM error field | Stability & Disruption Avoidance | CRPP-EPFL | Yes | No | No | |
| 76 details | Connection between particle and momentum transport | Turbulence & Transport | The college of William and Mary | Yes | Yes | Yes | |
| 77 details | Influence of rotation and rotation shear on ELM suppression | ELM Control | The college of William and Mary | Yes | No | No | |
| 78 details | 3D magnetics plasma response measurements of n=1 perturbations for RWM analysis & model validation | Stability & Disruption Avoidance | Department of Energy | Yes | No | Yes | |
| 79 details | 3D magnetics equilibrium measurements to applied n=3 perturbations | Stability & Disruption Avoidance | Department of Energy | Yes | No | Yes | |
| 80 details | Poloidal spectral measurements of n=3 RMP ELM suppression using the 3D magnetics upgrade | ELM Control | Department of Energy | Yes | No | Yes | |
| 83 details | Establishing stationary I-mode with high performance | ELM Control | Massachusetts Institute of Technology | Yes | Yes | No | |
| 84 details | 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 details | Current profile control for stable ITER baseline scenario plasmas | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |
| 87 details | 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 details | 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 details | Mo, W, Al, Be DiMES net/gross erosion experiments | Plasma-material Interface | U of Toronto | Yes | Yes | Yes | |
| 91 details | Complete the Development of PCS n=2 Error Field Control Algorithm | Stability & Disruption Avoidance | Department of Energy | Yes | No | No | |
| 92 details | H-mode Optimization of n=1&2 Error Field Control Currents | Stability & Disruption Avoidance | Department of Energy | Yes | No | No | |
| 93 details | Active Control of the EHO in Quiescent H-modes | Plasma Control | Department of Energy | Yes | No | No | |
| 97 details | Time-resolved measurement of plasma response spectrum | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |
| 98 details | Develop feedback-controlled MHD spectroscopy | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |
| 99 details | Understand and control resistive wall mode stability in high-qmin plasmas | Stability & Disruption Avoidance | Columbia U | Yes | Yes | No | |
| 100 details | Understand resistive wall mode control physics in low-q95 plasmas | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |
| 101 details | Investigation of n=1 RMP effects on ELMs with pitch-aligned configuration of I-coils | ELM Control | PPPL | Yes | Yes | Yes | |
| 102 details | TBM mock-up effects on confinement at high β | Stability & Disruption Avoidance | ITER Organization | Yes | No | Yes | |
| 103 details | 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 details | Comparision of small-ELM regimes in DIII-D and NSTX | ELM Control | U of Wisconsin | Yes | No | No | |
| 105 details | Optimization and exploration of the q95<2 scenario in DIII-D | Stability & Disruption Avoidance | Consorzio RFX | Yes | No | No | |
| 106 details | Magnetic turbulence measurements in high beta H-mode discharges | Turbulence & Transport | PPPL | Yes | No | No | |
| 107 details | Error field detection by application of a "spiraling" error field | Stability & Disruption Avoidance | ORNL | Yes | No | No | |
| 108 details | Disruption avoidance by forced magnetic spin-up of NTMs | Stability & Disruption Avoidance | ORNL | Yes | No | No | |
| 109 details | 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 details | 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 details | Dependence of I-mode on current direction and heating mix | ELM Control | Massachusetts Institute of Technology | Yes | Yes | No | |
| 112 details | 2D imaging of small ELMs | ELM Control | Los Alamos National Laboratory | Yes | No | No | |
| 113 details | 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 details | Toroidal peaking of radiation, response time for triggering TQ and mitigation efficiency during mass | Disruption Mitigation | ITER Organization | Yes | No | Yes | |
| 116 details | Influence of non-axisymmetric fields (TBMs / RMPs) on fast ion confinement and loss | Energetic Particles | ITER Organization | Yes | Yes | Yes | |
| 117 details | Conditions for nonlinear Alfvén Eigenmode evolution and impact on fast ion confinement and loss | Energetic Particles | ITER Organization | Yes | Yes | Yes | |
| 118 details | Dominant electron heated ITER baseline scenario studies | Inductive Scenarios | Columbia U | Yes | No | No | |
| 119 details | Impact of fast-ions on the RWM stability boundary | Stability & Disruption Avoidance | Columbia U | Yes | Yes | No | |
| 121 details | Testing Emerging Two-Fluid Model for RMP Plasma Response in Straightforward IWL Plasmas | ELM Control | ORNL | Yes | No | No | |
| 122 details | Bid farewell to locked modes - NTM-locking avoidance by feedback synchronization assisted with ECCD | Stability & Disruption Avoidance | PPPL | Yes | No | No | |
| 126 details | Triggering ELMs at high frequency with PPPL Lithium granule injector | ELM Control | Retired from PPPL | Yes | No | No | |
| 127 details | Characterization of Intense Bursts of Millimeter Wave Emission in QH-mode Plasma | Inductive Scenarios | UC, Davis | Yes | No | No | |
| 129 details | Optimization and Control of ITER-like MGI | Disruption Mitigation | GA | Yes | Yes | Yes | |
| 131 details | Understanding runaway equilibrium to minimize damage hazard | Disruption Mitigation | Yes | Yes | Yes | ||
| 133 details | Fast Runaway Shutdowns by MGI | Disruption Mitigation | GA | Yes | Yes | Yes | |
| 134 details | Pedestal stability and divertor transport studies with feedback-controlled snowflake configuration. | Divertor & SOL Physics | LLNL | Yes | No | No | |
| 137 details | 3D material migration during RMP ELM suppression | ELM Control | U of Wisconsin | Yes | Yes | Yes | |
| 142 details | ELM heat transport in the snowflake divertor. | Divertor & SOL Physics | LLNL | Yes | No | No | |
| 143 details | RMP ELM control at low torque | ELM Control | UCSD | Yes | No | No | |
| 144 details | 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 details | ELM suppression with Saturated walls | ELM Control | UCSD | Yes | No | No | |
| 147 details | Natural and Pellet-induced ELM behavior at low rotation/torque | ELM Control | UCSD | Yes | No | No | |
| 148 details | Radiative divertor control development | Divertor & SOL Physics | LLNL | Yes | No | No | |
| 153 details | Controlling VH-mode with RMPs and comparison to NSTX EPH-mode | ELM Control | ORNL | Yes | No | No | |
| 156 details | Controlling the timing and evolution of L-H and H-L with 3D fields | Plasma Control | PPPL | Yes | No | No | |
| 159 details | Collisionality dependence of pedestal height with RMP | Pedestal Structure | GA | Yes | No | No | |
| 163 details | Exploration of DEFC in the feedback stabilized plasma in low-q discharges | Stability & Disruption Avoidance | PPPL | Yes | No | No | |
| 177 details | Possibility of â??Off-axis-Fishbone Mode and ELM Pacingâ?? due to Direct Energetic Particle Coupling | ELM Control | PPPL | Yes | No | No | |
| 183 details | Measurement of multiple mechanisms in the low-density limit via ellipticity in the compass scan | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |
| 185 details | Measure Plasma Response to RMPs | ELM Control | GA | Yes | No | No | |
| 186 details | Optimal Mixing of I & C coils for n=1 EFC | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |
| 187 details | 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 details | Critical electric field for runaway electron growth and decay under quiescent conditions | Disruption Mitigation | Columbia U | Yes | Yes | No | |
| 193 details | Magnetic perturbation amplitude scan to investigate RMP-induced damping of Zonal Flows | Turbulence & Transport | U of Wisconsin | Yes | No | No | |
| 196 details | Narrow heat flux widths and divertor power dissipation | Divertor & SOL Physics | GA | Yes | Yes | Yes | |
| 197 details | Scaling of divertor detachment onset | Divertor & SOL Physics | GA | Yes | No | No | |
| 198 details | Compare the power threshold for pre-emptive NTM suppression vs Catch and Subdue | Stability & Disruption Avoidance | PPPL | Yes | No | No | |
| 199 details | Reducing the tearing island detection time | Stability & Disruption Avoidance | PPPL | Yes | No | No | |
| 200 details | Multiple periods of NTM suppression | Stability & Disruption Avoidance | PPPL | Yes | No | No | |
| 201 details | NTM Control Upgrade: Capibility to deposit EC at multiple locations | Plasma Control | PPPL | Yes | No | No | |
| 202 details | Error Field Correction Improvement: Adding BetaN dependence | Stability & Disruption Avoidance | PPPL | Yes | No | No | |
| 203 details | Dynamic plasma-wall equilibrium in ELMy H-mode | Divertor & SOL Physics | CompX | Yes | No | No | |
| 208 details | qmin control | Steady State Heating and Current Drive | PPPL | Yes | No | No | |
| 209 details | RMP ELM-Control for Snowflake Configurations | Torkil Jensen Award | LLNL | Yes | No | No | |
| 211 details | Control of experimentally simulated burning state | Plasma Control | QST | Yes | No | No | |
| 212 details | Island seeding with saw teeth pacing: New method to control tearing modes | Stability & Disruption Avoidance | PPPL | Yes | No | No | |
| 213 details | Real-time Ray Tracing for PCS | Plasma Control | PPPL | Yes | No | No | |
| 214 details | Density (Greenwald) Limit and the Radiation Driven Islands | Torkil Jensen Award | PPPL | Yes | No | No | |
| 216 details | Campaign to study physics at the Greenwald limit | Steady State Heating and Current Drive | PPPL | Yes | No | No | |
| 217 details | PID (proportional integral derivative)control of Error Field | Stability & Disruption Avoidance | PPPL | Yes | No | No | |
| 218 details | Controlled Snowflake Divertor Study | Divertor & SOL Physics | PPPL | Yes | No | No | |
| 221 details | Gas Injection Feedback with Radiation Measurements | Divertor & SOL Physics | PPPL | Yes | No | No | |
| 222 details | Investigation of optimum pellet injection geometry for pellet triggering minimum throughput/PFC flux | ELM Control | ITER Organization | Yes | No | Yes | |
| 223 details | Demonstration of integrated ELM-paced pellet fuelled H-mode plasma in ITER-relevant range. | ELM Control | ITER Organization | Yes | Yes | Yes | |
| 224 details | Determination of minimum confinement degradation for ELM suppression with I coils | ELM Control | ITER Organization | Yes | No | Yes | |
| 225 details | Study of atomic and molecular processes in deep detachment conditions | Divertor & SOL Physics | LLNL | Yes | No | No | |
| 226 details | Compatibility of ELM suppressed regimes by 3-D fields with pellet injection for plasma fuelling | ELM Control | ITER Organization | Yes | No | Yes | |
| 227 details | Mechanisms leading to termination of the runaway discharges and effects on PFC energy deposition | Disruption Mitigation | ITER Organization | Yes | No | Yes | |
| 228 details | High resolution study of collisionality and target structure in the transition to full detachment | Divertor & SOL Physics | LLNL | Yes | No | No | |
| 229 details | CQ de-confinement of REs using pulsed impurity injection | Disruption Mitigation | ITER Organization | Yes | No | Yes | |
| 230 details | Assessment of the degree of detachment using NIR spectroscopy | Divertor & SOL Physics | LLNL | Yes | No | No | |
| 232 details | Bifurcated helical core equilibrium - continued | Stability & Disruption Avoidance | U of Wisconsin | Yes | No | No | |
| 237 details | Critical electric field for runaway electron growth and decay under quiescent conditions | Disruption Mitigation | Massachusetts Institute of Technology | Yes | Yes | No | |
| 238 details | Direct Measurement of NTV Torque | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |
| 239 details | Continuous Scan of NTV Torque Across Low Rotation Peak | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |
| 240 details | Optimization of Applied Error Field Spectrum for NTV | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |
| 255 details | Super H-Mode | Torkil Jensen Award | ORNL | Yes | No | No | |
| 270 details | L-mode Turbulence and L-H Transition Characterization in Snowflake Divertor Plasmas | Divertor & SOL Physics | LLNL | Yes | No | No | |
| 271 details | Investigation of Momentum transport with Modulated ECH and ECH resonance layer sweeping | Plasma Rotation | National Fusion Research Institute (NFRI), Korea | Yes | Yes | Yes | |
| 272 details | Dither injection for closed-loop system identification of vacuum and plasma response | Torkil Jensen Award | KTH | Yes | No | No | |
| 273 details | Sawtooth control via n=1 external magnetic perturbation | Torkil Jensen Award | Consorzio RFX and Padova U | Yes | No | No | |
| 274 details | Investigation of Momentum transport with Modulated ECH and ECH resonance layer sweeping | Plasma Rotation | National Fusion Research Institute | Yes | Yes | Yes | |
| 275 details | Investigation of Momentum transport with Modulated ECH and ECH resonance layer sweeping | Plasma Rotation | National Fusion Research Institute | Yes | Yes | Yes | |
| 276 details | 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 details | ECH effects on low or balanced torque discharges in DIII-D | Plasma Rotation | National Fusion Research Institute (NFRI), Korea | Yes | Yes | No | |
| 279 details | ECH effects on low or balanced torque discharges in DIII-D | Plasma Rotation | National Fusion Research Institute (NFRI), Korea | Yes | Yes | No | |
| 281 details | ECH effects on low or balanced torque discharges in DIII-D | Plasma Rotation | National Fusion Research Institute (NFRI), Korea | Yes | Yes | No | |
| 282 details | 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 details | Determine dependence of RWM marginal stability on rotation and energetic particles | Stability & Disruption Avoidance | Columbia U | Yes | Yes | Yes | |
| 301 details | Access to the small ELM regime with a shape control | ELM Control | ORNL | Yes | No | No | |
| 341 details | 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 details | Investigation of Momentum transport with Modulated ECH and ECH resonance layer scan | Plasma Rotation | National Fusion Research Institute | Yes | Yes | Yes |