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 |
||
3 | The effect of LSN Shape on the q95 windows in RMP ELM Suppression | ELM Control | GA | No | No | Yes | |||
25 | Transport mechanisms induced by RMP | ELM Control | UCSD | No | No | Yes | |||
49 | Turbulent transport in detached divertor | Divertor & SOL Physics | UCSD | No | No | Yes | |||
58 | Progressing Towards a Staged Approach to Disruption Mitigation | Disruption Mitigation | GA | Yes | No | Yes | |||
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 | |||
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 | |||
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 | |||
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 | |||
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 | |||
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 | ||||
132 | Dissipation & Control of RE from ITER-like LSN targets | Disruption Mitigation | GA | No | No | Yes | |||
133 | Fast Runaway Shutdowns by MGI | Disruption Mitigation | GA | Yes | Yes | Yes | |||
135 | Measurement of RE diffusion to center post | Disruption Mitigation | UCSD | No | No | 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 | |||
139 | TQ radiation distribution from R-2 MGI | Disruption Mitigation | UCSD | No | No | Yes | |||
141 | Studies of RE final loss | Disruption Mitigation | UCSD | No | No | Yes | |||
154 | High frequency pellet ELM pacing | ELM Control | ORNL | No | Yes | Yes | |||
155 | Investigation of pellet induced ELM heat flux footprint variation with q95 | ELM Control | ORNL | No | No | Yes | |||
157 | Imaging of pellet induced ELM events from mulitple simultaneous views. | ELM Control | ORNL | No | No | Yes | |||
161 | n=3 offset and ELM suppression with RMP | ELM Control | GA | No | No | Yes | |||
165 | D2 + few % Ne shattered pellets for disruption mitigation | Disruption Mitigation | ORNL | No | No | Yes | |||
166 | Effect of q95 on SPI shutdown | Disruption Mitigation | ORNL | No | No | Yes | |||
167 | Control of radiation asymmetries by application of external field on SPI/MGI shutdown | Disruption Mitigation | ORNL | No | No | Yes | |||
168 | Influence of the delay time between multiple massive gas injections at different toroidal locations | Disruption Mitigation | ORNL | No | No | Yes | |||
169 | Runaway flattop mitigation by Neon shattered pellet injection | Disruption Mitigation | ORNL | No | No | Yes | |||
171 | Test of the argon pellet injector | Disruption Mitigation | ORNL | No | No | 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 | |||
196 | Narrow heat flux widths and divertor power dissipation | Divertor & SOL Physics | GA | Yes | Yes | Yes | |||
204 | Suppression of Density Limit Disruptions with RMP Fields | Torkil Jensen Award | GA | No | No | Yes | |||
205 | SOL width in top-limited discharges | Divertor & SOL Physics | UCSD | No | No | 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 | |||
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 | |||
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 | |||
229 | CQ de-confinement of REs using pulsed impurity injection | Disruption Mitigation | ITER Organization | Yes | No | Yes | |||
250 | Plateau Ecrit with MGI | Disruption Mitigation | GA | No | Yes | Yes | |||
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 | |||
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 | |||
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 | |||
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 | |||
338 | Local correction of the TBM error field | Stability & Disruption Avoidance | Columbia U | No | No | Yes | |||
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 | |||
343 | Evaluating Physics of RMP Stationary Enhanced Confinement Regime Without ELMs for the 2013 JRT | ELM Control | LLNL | No | No | Yes | |||
358 | Investigation of Momentum transport with Modulated ECH and ECH resonance layer scan | Plasma Rotation | National Fusion Research Institute | Yes | Yes | Yes | |||
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 | |||
398 | TQ radiation distribution from R-2 MGI | Disruption Mitigation | UCSD | No | No | Yes | |||
399 | TQ radiation distribution from R-2 MGI | Disruption Mitigation | UCSD | No | No | Yes | |||
407 | n-scaling of magnetic errors (TBM related) | Plasma Rotation | GA | No | No | Yes | |||
410 | Sensitivity of RMP ELM Suppression with Less Than 12 I-coils to I-coil Configuration | ELM Control | LLNL | No | No | Yes | |||
418 | Mapping the current rise stability boundary for the ITER baseline scenario | Inductive Scenarios | ITER Organization | No | No | Yes | |||
453 | Minimize Density Pumpout During RMP ELM Suppression | ELM Control | LLNL | No | No | Yes | |||
455 | TBM mock-up effects on confinement at high β | Stability & Disruption Avoidance | ITER Organization | Yes | No | Yes | |||
458 | Test optimized TBM error field correction at higher values of beta | Stability & Disruption Avoidance | CRPP-EPFL | No | No | Yes | |||
460 | Quantifying the TBM torque, both in magnitude and radial location | Plasma Rotation | VTT Technical Research Centre | No | 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 | |||
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 | |||
508 | ITER Baseline Scenario in a Radiating Divertor Environment with near-Zero Applied Torque | Inductive Scenarios | GA | No | No | Yes | |||
512 | Best Impurity Specie for the Radiating Divertor in the ITER Baseline Scenario with near-Zero Torque | Inductive Scenarios | GA | No | No | Yes | |||
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 | |||
532 | Role of ECH Induced Mulitiscale Electron Thermal Transport in H-mode Plasmas | Turbulence & Transport | Massachusetts Institute of Technology | No | No | Yes | |||
535 | Main-ion and impurity neoclassical flows compared with the PERFECT pedestal code | Pedestal Structure | Massachusetts Institute of Technology | No | No | Yes | |||
549 | Testing kinetic RWM stabilization theory at marginal stability in high beta, TM stabilized plasmas | Stability & Disruption Avoidance | Columbia U | Yes | Yes | Yes | |||
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 | |||
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 | |||
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 | |||
631 | Optimization of RMP pedestal with feedback control | ELM Control | GA | Yes | No | Yes | |||
634 | Mitigation: Reduction of toroidal-asymmetry of radiation loss by 3D-magnetic mode rotation control | Disruption Mitigation | PPPL | No | No | Yes | |||
635 | Mitigation: pellet and massive gas injections in helically favorable ways for reducing asymmetry | Disruption Mitigation | PPPL | No | No | Yes | |||
647 | Radiating Divertor Applied to the ITER Baseline Scenario at near-Zero Applied Torque | Divertor & SOL Physics | GA | No | No | Yes | |||
648 | Determining the Optimal Impurity Specie for the Radiating Divertor in the ITER Baseline Scenario | Divertor & SOL Physics | GA | No | No | Yes | |||
676 | Robust NTM control | Plasma Control | CRPP-EPFL | No | Yes | Yes | |||
677 | Robust NTM control | Stability & Disruption Avoidance | CRPP-EPFL | No | Yes | Yes | |||
712 | D2 + few % Ne shattered pellets for disruption mitigation | Disruption Mitigation | ORNL | No | No | Yes | |||
713 | Control of radiation asymmetries by application of external field on SPI/MGI shutdown | Disruption Mitigation | ORNL | No | No | Yes | |||
714 | Runaway flattop mitigation by Neon shattered pellet injection | Disruption Mitigation | ORNL | No | No | Yes | |||
735 | ELM Suppression in Helium Plasmas | ELM Control | GA | No | No | Yes | |||
739 | Reduce L-H treshold power in H plasmas using pellet injection | L-H Transition | GA | No | No | Yes | |||
746 | Isotope dependence of Pthr and edge turbulence at L-H and H-L transition in DIII-D and JET-ILW | L-H Transition | IPP Garching | No | No | Yes | |||
755 | Heat flux footprint with pellet-paced ELMs vs nustar | ELM Control | PPPL | No | No | Yes |