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 |
||
48 | Dependence of momentum transport and intrinsic torque on rho* and beta | Plasma Rotation | VTT Technical Research Centre | No | Yes | No | |||
51 | Study of chirping Alfvén eigenmodes in DIII-D | Energetic Particles | PPPL | No | Yes | 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 | |||
76 | Connection between particle and momentum transport | Turbulence & Transport | The college of William and Mary | Yes | Yes | Yes | |||
82 | IR Imaging of I-coil Induced Fast Ion Losses | Energetic Particles | GA | No | Yes | No | |||
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 | |||
89 | Mo, W, Al, Be DiMES net/gross erosion experiments | Plasma-material Interface | U of Toronto | Yes | Yes | Yes | |||
99 | Understand and control resistive wall mode stability in high-qmin plasmas | Stability & Disruption Avoidance | Columbia U | Yes | Yes | No | |||
101 | Investigation of n=1 RMP effects on ELMs with pitch-aligned configuration of I-coils | ELM Control | PPPL | Yes | Yes | Yes | |||
111 | Dependence of I-mode on current direction and heating mix | ELM Control | Massachusetts Institute of Technology | Yes | Yes | No | |||
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 | |||
119 | Impact of fast-ions on the RWM stability boundary | Stability & Disruption Avoidance | Columbia U | Yes | Yes | No | |||
129 | Optimization and Control of ITER-like MGI | Disruption Mitigation | GA | Yes | Yes | Yes | |||
130 | Synergy between core-localized Alfven eigenmodes and edge localized TBM fields on fast ion losses. | Energetic Particles | PPPL | No | Yes | No | |||
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 | |||
136 | Disruption main chamber heat loads | Disruption Mitigation | UCSD | No | Yes | Yes | |||
137 | 3D material migration during RMP ELM suppression | ELM Control | U of Wisconsin | Yes | Yes | Yes | |||
154 | High frequency pellet ELM pacing | ELM Control | ORNL | No | Yes | Yes | |||
181 | Heat pulse propagation in a perturbed magnetic topology | ELM Control | GA | No | Yes | Yes | |||
184 | Comparision DIII-D and AUG high collisionality ELM response to 3D magnetic perturbations | ELM Control | GA | No | Yes | Yes | |||
191 | Critical electric field for runaway electron growth and decay under quiescent conditions | Disruption Mitigation | Columbia U | Yes | Yes | No | |||
196 | Narrow heat flux widths and divertor power dissipation | Divertor & SOL Physics | GA | Yes | Yes | Yes | |||
220 | Comparison of n=2 RMP field effects on ELMs and pedestal properties in KSTAR and DIII-D | ELM Control | GA | No | Yes | Yes | |||
223 | Demonstration of integrated ELM-paced pellet fuelled H-mode plasma in ITER-relevant range. | ELM Control | ITER Organization | Yes | Yes | Yes | |||
231 | Stabilization of NTMs with ECCD | Stability & Disruption Avoidance | QST | No | Yes | No | |||
237 | Critical electric field for runaway electron growth and decay under quiescent conditions | Disruption Mitigation | Massachusetts Institute of Technology | Yes | Yes | No | |||
250 | Plateau Ecrit with MGI | Disruption Mitigation | GA | No | Yes | Yes | |||
257 | Transport Investigation During Slow Current Ramp-Up and Ramp-Down [for ITER] | Inductive Scenarios | U of Wisconsin | No | Yes | No | |||
260 | ITER Baseline Scenario Demonstration | Inductive Scenarios | ITER Organization | No | Yes | No | |||
263 | Radiative divertor solutions in the ITER baseline scenario | Inductive Scenarios | ITER Organization | No | Yes | Yes | |||
264 | Radiative divertor solutions in the ITER baseline scenario | Divertor & SOL Physics | ITER Organization | No | Yes | Yes | |||
268 | nu* dimensionless scaling | Turbulence & Transport | CEA | No | Yes | 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 | |||
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 | |||
283 | ITER Baseline Scenario Operation near the LH Threshold | Inductive Scenarios | ITER Organization | No | Yes | No | |||
284 | Access conditions for steady-state operation in ITER | Steady State Heating and Current Drive | ITER Organization | No | Yes | No | |||
285 | Access to advanced inductive operation in ITER | Inductive Scenarios | ITER Organization | No | Yes | No | |||
286 | Collisionality scaling of confinement in advanced inductive regimes | Inductive Scenarios | ITER Organization | No | Yes | No | |||
296 | Determine dependence of RWM marginal stability on rotation and energetic particles | Stability & Disruption Avoidance | Columbia U | Yes | Yes | Yes | |||
309 | Full 3D Rotation optimization of H mode | Stability & Disruption Avoidance | GA | No | Yes | Yes | |||
314 | Optimization of castellation for a new W-divertor of ITER: studies of shaped castellation in DIII-D | Plasma-material Interface | UCSD | No | Yes | Yes | |||
327 | rho* scaling of intrinsic torque between DIII-D and JET | Plasma Rotation | GA | No | Yes | No | |||
339 | Combined effect of TBM and NTM fields on fast-ion confinement | Stability & Disruption Avoidance | UC, Irvine | No | Yes | No | |||
340 | Combined effect of TBM and Sawtooth fields on fast-ion confinement | Stability & Disruption Avoidance | UC, Irvine | No | Yes | 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 | |||
342 | Investigation of Core Poloidal Rotation Anomaly Change at ITG -> TEM transition | Plasma Rotation | National Fusion Research Institute (NFRI) | No | Yes | Yes | |||
358 | Investigation of Momentum transport with Modulated ECH and ECH resonance layer scan | Plasma Rotation | National Fusion Research Institute | Yes | Yes | Yes | |||
362 | Investigation of GAMs during I-mode on D3D | Turbulence & Transport | Massachusetts Institute of Technology | No | Yes | No | |||
367 | JET/DIII-D similarity experiment on rotation in plasmas with low momentum input | Plasma Rotation | Instituto Superior Tecnico, Lisboa, Portugal | No | Yes | No | |||
368 | Investigation of extreme outer wall heating caused by the DIII-D TBM | Plasma-material Interface | LLNL | No | Yes | Yes | |||
397 | Disruption main chamber heat loads | Disruption Mitigation | UCSD | No | Yes | Yes | |||
401 | ITER Baseline Scenario Demonstration | Inductive Scenarios | ITER Organization | No | Yes | No | |||
402 | Radiative divertor solutions in the ITER baseline scenario | Inductive Scenarios | ITER Organization | No | Yes | No | |||
403 | Radiative divertor solutions in the ITER baseline scenario | Divertor & SOL Physics | ITER Organization | No | Yes | No | |||
404 | ITER Baseline Scenario Operation near the LH Threshold | Inductive Scenarios | ITER Organization | No | Yes | No | |||
405 | Access conditions for steady-state operation in ITER | Steady State Heating and Current Drive | ITER Organization | No | Yes | No | |||
406 | Fast-ion and thermal transport at high qmin | Steady State Heating and Current Drive | ITER Organization | No | Yes | No | |||
408 | Access to advanced inductive operation in ITER | Inductive Scenarios | ITER Organization | No | Yes | No | |||
409 | Collisionality scaling of confinement in advanced inductive regimes | Inductive Scenarios | ITER Organization | No | Yes | No | |||
416 | Burn Control in ITER Baseline Scenario | Inductive Scenarios | ITER Organization | No | Yes | No | |||
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 | |||
425 | Flow or flow shear for m/n=2/1 tearing mode stabilization? | Stability & Disruption Avoidance | Retired from GA | Yes | Yes | No | |||
454 | Synergy between core-localized Alfven eigenmodes and edge localized TBM fields on fast ion losses. | Energetic Particles | PPPL | No | Yes | No | |||
461 | Dependence of momentum transport and intrinsic torque on rho* and beta | Plasma Rotation | VTT Technical Research Centre | No | Yes | No | |||
474 | 3D material migration during RMP ELM suppression | Plasma-material Interface | U of Wisconsin | Yes | Yes | No | |||
498 | Validation of single-mode model of error field correction for n=2 fields | Stability & Disruption Avoidance | Department of Energy | Yes | Yes | No | |||
514 | LOC/SOC Studies | Turbulence & Transport | MIT PSFC | Yes | Yes | No | |||
522 | Combined effect of TBM and NTM fields on fast-ion confinement | Energetic Particles | UC, Irvine | No | Yes | No | |||
523 | Combined effect of TBM and Sawtooth fields on fast-ion confinement | Energetic Particles | UC, Irvine | No | Yes | No | |||
549 | Testing kinetic RWM stabilization theory at marginal stability in high beta, TM stabilized plasmas | Stability & Disruption Avoidance | Columbia U | Yes | Yes | Yes | |||
579 | Mapping of Peeling Mode Stability Boundary | Pedestal Structure | GA | No | Yes | No | |||
580 | Collisionality/density dependence and Pedestal optimization with ELM Sup | ELM Control | GA | No | Yes | No | |||
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 | |||
587 | Demonstration of integrated ELM-paced pellet fuelled H-mode plasma in ITER-relevant range. | ELM Control | ITER Organization | Yes | Yes | Yes | |||
592 | ECH Control of Alfven Eigenmodes | Energetic Particles | ITER Organization | Yes | Yes | Yes | |||
612 | Investigate the Impact of ECH on Alfvenic Activity | Energetic Particles | GA | No | Yes | No | |||
646 | rho* scaling of intrinsic torque between DIII-D and JET | Plasma Rotation | GA | No | Yes | No | |||
655 | ECH effects on QH-mode low or balanced torque discharges in DIII-D | Plasma Rotation | Korea Institute of Fusion Energy | No | Yes | No | |||
675 | Error field correction at low rotation | Stability & Disruption Avoidance | GA | No | Yes | No | |||
676 | Robust NTM control | Plasma Control | CRPP-EPFL | No | Yes | Yes | |||
677 | Robust NTM control | Stability & Disruption Avoidance | CRPP-EPFL | No | Yes | Yes | |||
688 | Measure Beam Ion Transport due to Resonance Between Applied 3D Fields and Injected Beam Ion Orbits | Energetic Particles | GA | No | Yes | No | |||
694 | Image Heat Load Due to Prompt and 3D field Induced EP Losses | Energetic Particles | GA | No | Yes | No | |||
696 | Measure Change in 3D Field Induced EP Losses Due to Screening | Energetic Particles | GA | No | Yes | No | |||
729 | Dependence of pedestal structure on collisionality and Zeff in relation to JET results with ILW | Pedestal Structure | GA | No | Yes | No | |||
751 | Dimensionless Identity Experiments in I-Mode with C-Mod and AUG (TC-18) | Pedestal Structure | Massachusetts Institute of Technology | No | Yes | No | |||
752 | Divertor detachment versus toroidal field and plasma current | Divertor & SOL Physics | GA | No | Yes | No |