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 |
||
58 | Progressing Towards a Staged Approach to Disruption Mitigation | Disruption Mitigation | GA | Yes | No | Yes | |||
608 | Quiescent runaway electron studies for 2014 | Disruption Mitigation | Columbia U | No | No | No | |||
609 | MHD spectroscopy and poloidal coupling of plateau RE plasmas | Disruption Mitigation | Columbia U | No | No | No | |||
191 | Critical electric field for runaway electron growth and decay under quiescent conditions | Disruption Mitigation | Columbia U | Yes | Yes | No | |||
747 | Dissipation & Control of RE from ITER-like LSN targets | Disruption Mitigation | GA | No | No | No | |||
749 | Neon SPI injection into early CQ to stunt RE formation | Disruption Mitigation | GA | No | No | No | |||
132 | Dissipation & Control of RE from ITER-like LSN targets | Disruption Mitigation | GA | No | No | Yes | |||
254 | Neon SPI injection into early CQ to stunt RE formation | Disruption Mitigation | GA | No | No | No | |||
661 | Massive gas injection into an unstable plasma | Disruption Mitigation | GA | No | No | No | |||
250 | Plateau Ecrit with MGI | Disruption Mitigation | GA | No | Yes | Yes | |||
129 | Optimization and Control of ITER-like MGI | Disruption Mitigation | GA | Yes | Yes | Yes | |||
133 | Fast Runaway Shutdowns by MGI | Disruption Mitigation | GA | Yes | Yes | Yes | |||
237 | Critical electric field for runaway electron growth and decay under quiescent conditions | Disruption Mitigation | Massachusetts Institute of Technology | Yes | Yes | No | |||
437 | TQ radiation distribution from R-2 MGI | Disruption Mitigation | Massachusetts Institute of Technology | No | No | No | |||
171 | Test of the argon pellet injector | Disruption Mitigation | ORNL | 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 | |||
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 | |||
715 | Test of the upgraded SPI | Disruption Mitigation | ORNL | No | No | No | |||
767 | Radiation asymmetry measurements in opposite-handed plasmas | Disruption Mitigation | ORNL | No | No | No | |||
517 | Physics of Crescent-shaped synchrotron emission patterns in runaway plateau dischar | Disruption Mitigation | UCSD | Yes | No | No | |||
506 | Understanding the synchrotron emission patterns in QRE discharges | Disruption Mitigation | UCSD | Yes | No | No | |||
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 | |||
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 | |||
396 | Measurement of RE diffusion to center post | Disruption Mitigation | UCSD | No | No | No | |||
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 | |||
400 | Studies of RE final loss | Disruption Mitigation | UCSD | No | No | No | |||
625 | Disruption Precursor Identification | Disruption Mitigation | U of Colorado, Boulder | No | No | No | |||
583 | Dissipation of runaway energy by high-Z impurity injection | Disruption Mitigation | ITER Organization | Yes | Yes | 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 | |||
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 | |||
131 | Understanding runaway equilibrium to minimize damage hazard | Disruption Mitigation | Yes | Yes | Yes | ||||
377 | NTM locking disruption avoidance by the EM torque with toroidal-phase forward magnetic feed | Disruption Mitigation | PPPL | No | No | No | |||
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 | |||
150 | Sensitivity study of toroidally-asymmetric halo current to error field during VDE | Disruption Mitigation | PPPL | No | No | No | |||
40 | MGI with applied n=1 RMP fields | Disruption Mitigation | Fiat Lux LLC | No | No | No | |||
21 | Magnitude of cross-field drifts in the Private Flux Region, divertor asymmetries and detachment | Divertor & SOL Physics | Aalto U | No | No | No | |||
22 | Assessment of main chamber carbon sources | Divertor & SOL Physics | Aalto U | No | No | No | |||
777 | Magnitude of cross-field drifts in the Private Flux Region, divertor asymmetries and detachment | Divertor & SOL Physics | Aalto U | No | No | No | |||
778 | Assessment of main chamber carbon sources | Divertor & SOL Physics | Aalto U | No | No | No | |||
723 | Physics of the Heat Flux Width | Divertor & SOL Physics | AKIMA Infrastructure Services | No | No | No | |||
559 | SOL Width Scaling: Goldston's Heuristic Drift Model vs Critical Pressure Gradient Model | Divertor & SOL Physics | PPPL | No | No | No | |||
561 | Interaction of RMP Snowflake Divertor | Divertor & SOL Physics | PPPL | No | 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 | |||
642 | Gas Injection Feedback with Radiation Measurements | Divertor & SOL Physics | PPPL | No | No | No | |||
644 | Controlled Snowflake Divertor Study | Divertor & SOL Physics | PPPL | No | No | No | |||
790 | Detachment Control for H-mode | Divertor & SOL Physics | PPPL | No | No | No | |||
788 | Optimize Radiative Divertor and Core Performance | Divertor & SOL Physics | PPPL | No | No | No | |||
620 | Measurement of heat flux on the divertor using the embedded thermocouple array | Divertor & SOL Physics | U of Tennessee, Knoxville | No | No | No | |||
621 | Investigation of Sheath Power Transmission at the DIII-D Divertor using Surface Thermocouples | Divertor & SOL Physics | U of Tennessee, Knoxville | No | No | No | |||
192 | Measurement of heat flux on the divertor using the embedded thermocouple array | Divertor & SOL Physics | U of Tennessee, Knoxville | No | No | No | |||
149 | Measurement of ion temperatures in the divertor region of DIII-D using the DiMES platform | Divertor & SOL Physics | U of Tennessee, Knoxville | No | No | No | |||
142 | ELM heat transport in the snowflake divertor. | Divertor & SOL Physics | LLNL | Yes | No | No | |||
148 | Radiative divertor control development | Divertor & SOL Physics | LLNL | Yes | No | No | |||
134 | Pedestal stability and divertor transport studies with feedback-controlled snowflake configuration. | Divertor & SOL Physics | LLNL | Yes | No | No | |||
519 | RMP ELM-Control for Snowflake Configurations | Divertor & SOL Physics | LLNL | No | No | No | |||
576 | Slow snowflake configuration scans to clarify geometry vs physics | Divertor & SOL Physics | LLNL | No | No | No | |||
577 | MARFE limits in the snowflake configuration | Divertor & SOL Physics | LLNL | No | No | No | |||
403 | Radiative divertor solutions in the ITER baseline scenario | Divertor & SOL Physics | ITER Organization | No | Yes | No | |||
230 | Assessment of the degree of detachment using NIR spectroscopy | Divertor & SOL Physics | LLNL | Yes | No | No | |||
225 | Study of atomic and molecular processes in deep detachment conditions | Divertor & SOL Physics | LLNL | Yes | No | No | |||
228 | High resolution study of collisionality and target structure in the transition to full detachment | Divertor & SOL Physics | LLNL | Yes | No | No | |||
264 | Radiative divertor solutions in the ITER baseline scenario | Divertor & SOL Physics | ITER Organization | No | Yes | Yes | |||
627 | Core edge integration for QH-mode plasmas in ITER | Divertor & SOL Physics | ITER Organization | Yes | No | Yes | |||
666 | Radiation limit in the snowflake configuration | Divertor & SOL Physics | CRPP-EPFL | No | No | No | |||
667 | Effect of the snowflake configuration on the SOL width in simple plasmas | Divertor & SOL Physics | CRPP-EPFL | No | No | No | |||
472 | Effect of divertor geometry & heating scheme on the characteristic widths of heat flux footprint | Divertor & SOL Physics | ASIPP | 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 | |||
431 | Turbulent transport in detached divertor | Divertor & SOL Physics | UCSD | No | No | No | |||
49 | Turbulent transport in detached divertor | Divertor & SOL Physics | UCSD | No | No | Yes | |||
27 | COupling between core and SOL parallel flow | Divertor & SOL Physics | UCSD | No | No | No | |||
434 | COupling between core and SOL parallel flow | Divertor & SOL Physics | UCSD | No | No | No | |||
772 | Unified edge and SOL rotation | Divertor & SOL Physics | UCSD | No | No | 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 | |||
62 | RMP assisted snowflake divertor | Divertor & SOL Physics | U of Wisconsin | Yes | No | No | |||
473 | RMP assisted snowflake divertor | Divertor & SOL Physics | U of Wisconsin | Yes | No | No | |||
520 | Effect of 3-D fields on divertor detachment | Divertor & SOL Physics | ORNL | Yes | No | No | |||
768 | sheath physics study 2 | Divertor & SOL Physics | Sandia National Lab | No | No | No | |||
769 | benchmark heat flux with fast TCs | Divertor & SOL Physics | Sandia National Lab | No | No | No | |||
265 | o Experiments using the centerpost Swing-probes | Divertor & SOL Physics | UCSD | No | No | No | |||
205 | SOL width in top-limited discharges | Divertor & SOL Physics | UCSD | No | No | Yes | |||
717 | Role of poloidal flux expansion to address divertor heat flux challenge | Divertor & SOL Physics | GA | No | 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 | |||
752 | Divertor detachment versus toroidal field and plasma current | Divertor & SOL Physics | GA | No | Yes | No | |||
203 | Dynamic plasma-wall equilibrium in ELMy H-mode | Divertor & SOL Physics | CompX | Yes | No | No | |||
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 | |||
674 | Assessing the Need for Using Two Impurity Species in Radiating Divertor | Divertor & SOL Physics | GA | No | No | No | |||
443 | Effect of Changing the Grad-B Drift Direction on Snowflake Divertor Behavior, Including Detachment | Divertor & SOL Physics | GA | No | No | No | |||
441 | Active Particle Exhaust of H-mode Plasmas in the Snowflake-minus Divertor Configuration | Divertor & SOL Physics | GA | No | No | No | |||
614 | Why Does the Heat Flux Increase in the Secondary Divertor Under the BetaN = constant Constraint? | Divertor & SOL Physics | GA | No | No | No | |||
81 | Active Particle Exhaust of H-mode Plasmas in the Snowflake-minus Divertor Configuration | Divertor & SOL Physics | GA | No | 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 | |||
59 | Effect of Changing the Grad-B Drift Direction on Snowflake Divertor Behavior, Including Detachment | Divertor & SOL Physics | GA | No | No | No | |||
641 | Using Magnetic Balance To Regulate Density and Impurity Accumulation Inside Double-null Plasmas | Divertor & SOL Physics | GA | No | No | No | |||
43 | Density Control and Active Impurity Removal from Double-null H-mode Plasmas | Divertor & SOL Physics | GA | No | No | No | |||
44 | Can Nitrogen impurity Seeding Improve Radiating Divertor Performance? | Divertor & SOL Physics | GA | No | No | No | |||
46 | Does Added Baffling From Re-Configured Tiles on the Lower Divertor Shelf Facilitate Detachment? | Divertor & SOL Physics | GA | No | No | No | |||
541 | Support of DIII-D boundary physics experiments | Divertor & SOL Physics | MIT | No | No | No | |||
542 | Investigations of advanced divertor configurations for DIII-D | Divertor & SOL Physics | MIT | No | No | No | |||
270 | L-mode Turbulence and L-H Transition Characterization in Snowflake Divertor Plasmas | Divertor & SOL Physics | LLNL | Yes | No | No | |||
306 | Edge turbulence and blob generation | Divertor & SOL Physics | Univ. Wisconsin | No | No | No | |||
278 | Possibility of â??Off-axis-Fishbone Mode and ELM Pacingâ?? due to Direct Energetic Particle Coupling | ELM Control | JAEA | No | No | No | |||
603 | Dominant poloidal modes for ELM suppression via n=2 upper/lower I-coil phase difference | ELM Control | Columbia U | No | No | No | |||
29 | Modulation of Bootstrap Current | ELM Control | GA | No | No | No | |||
45 | Differences in Impurity Accumulation Between Resonant and Non-resonant RMP Plasmas | ELM Control | GA | No | No | No | |||
302 | RMP ELM Suppression at the NTV Offset Rotation | ELM Control | GA | No | No | No | |||
371 | Effect of icoil current on energy confinement in RMP ELM-suppressed discharges | ELM Control | GA | No | No | No | |||
378 | Study of the connection between I-mode and low density Type III ELMs and optimization of I-mode | ELM Control | GA | No | No | No | |||
380 | ELM Suppression at Lower Collisionality with Non-Resonant n=3 I-coil | ELM Control | GA | No | No | No | |||
189 | Measurement of optimal n=2 phasing for RMP & ELM suppression without q95 windows | ELM Control | Columbia U | No | No | No | |||
190 | Measurement of n=3 error field effects in RMP phase-flip experiments | ELM Control | Columbia U | No | No | No | |||
702 | Measurement of hysteresis in RMP-ELM suppression thresholds | ELM Control | Columbia U | No | No | No | |||
798 | Density matching with and without ELMs. | ELM Control | GA | No | No | No | |||
185 | Measure Plasma Response to RMPs | ELM Control | GA | Yes | No | No | |||
552 | Modulation of Bootstrap Current | ELM Control | GA | No | No | No | |||
553 | Bootstrap Current Change During RMP ELM Suppression | ELM Control | GA | No | No | No | |||
555 | Measure Plasma Response to RMPs | ELM Control | GA | No | No | No | |||
19 | Effect of n=1 applied and error fields on n=3 RMP ELM suppression | ELM Control | GA | No | No | No | |||
3 | The effect of LSN Shape on the q95 windows in RMP ELM Suppression | ELM Control | GA | No | No | Yes | |||
23 | RMP ELM Suppression at q95 above 4 | ELM Control | GA | No | No | No | |||
385 | The effect of LSN Shape on the q95 windows in RMP ELM Suppression | ELM Control | GA | No | No | No | |||
724 | Impurity transport in ELM-suppressed regimes | ELM Control | GA | No | No | No | |||
513 | Investigating the role of inter-ELM fluctuations in the ELM trigger | ELM Control | GA | No | No | No | |||
701 | Effect of lithium conditioning on H-mode pedestal profiles and ELM stability | ELM Control | GA | No | No | No | |||
161 | n=3 offset and ELM suppression with RMP | ELM Control | GA | No | No | Yes | |||
580 | Collisionality/density dependence and Pedestal optimization with ELM Sup | ELM Control | GA | No | Yes | No | |||
584 | n=1 RMP Suppression and the role of field penetration vs kink excitation | ELM Control | GA | Yes | No | No | |||
631 | Optimization of RMP pedestal with feedback control | ELM Control | GA | Yes | No | Yes | |||
801 | Collisionality dependence of pedestal height with RMP | ELM Control | GA | No | No | No | |||
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 | |||
219 | Establishing an experimental basis for plasma effects on magnetic islands | ELM Control | GA | No | No | No | |||
220 | Comparison of n=2 RMP field effects on ELMs and pedestal properties in KSTAR and DIII-D | ELM Control | GA | No | Yes | Yes | |||
711 | Comparision DIII-D and AUG high collisionality ELM response to 3D magnetic perturbations | ELM Control | GA | No | No | No | |||
735 | ELM Suppression in Helium Plasmas | ELM Control | GA | No | No | Yes | |||
493 | Edge rotation shear threshold for QH-mode access | ELM Control | GA | No | No | No | |||
389 | Effect of n=1 applied and error fields on n=3 RMP ELM suppression | ELM Control | GA | No | No | No | |||
390 | RMP ELM Suppression at q95 above 4 | ELM Control | GA | No | No | No | |||
348 | Can we obtain ELM suppression without substantial loss of density? | ELM Control | UCLA | No | No | No | |||
235 | High resolution Te pedestal measurements in RMP ELM suppression experiments | ELM Control | Sandia National Lab | No | No | No | |||
563 | The Role of Energetic Particles in ELM-Free H-mode Plasmas | ELM Control | UC, Irvine | No | No | No | |||
301 | Access to the small ELM regime with a shape control | ELM Control | ORNL | Yes | No | No | |||
55 | RMP Elm Suppression in DN Plasmas | ELM Control | ORNL | No | No | No | |||
786 | Determining Particle Sources/Sinks in ITER-like NN Discharges during RMP ELM suppression | ELM Control | ORNL | No | No | 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 | |||
732 | Testing ELM destabilization by 3D fields on DIII-D | ELM Control | ORNL | No | No | No | |||
733 | Distinguishing between 3d magnetic field structures and transport | ELM Control | ORNL | No | No | No | |||
153 | Controlling VH-mode with RMPs and comparison to NSTX EPH-mode | ELM Control | ORNL | Yes | No | No | |||
590 | Targeting Top of Pedestal in RMP ELM-suppressed plasmas with SXR Imaging | ELM Control | ORNL | No | No | No | |||
588 | Plasma Response in IWL H-mode plasmas | ELM Control | ORNL | No | No | No | |||
121 | Testing Emerging Two-Fluid Model for RMP Plasma Response in Straightforward IWL Plasmas | ELM Control | ORNL | Yes | No | No | |||
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 | |||
83 | Establishing stationary I-mode with high performance | ELM Control | Massachusetts Institute of Technology | Yes | Yes | No | |||
616 | Validation of nonlinear models of ELMs and RMP ELM mitigation | ELM Control | Massachusetts Institute of Technology | 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 | |||
475 | Helium exhaust with 3D fields | ELM Control | U of Wisconsin | Yes | No | No | |||
137 | 3D material migration during RMP ELM suppression | ELM Control | U of Wisconsin | Yes | Yes | Yes | |||
305 | Scaling Of Pedestal Plasma Transport With RMP I-coil Current | ELM Control | U of Wisconsin | No | No | No | |||
727 | Scaling Of Pedestal Plasma Transport With RMP I-coil Current | ELM Control | U of Wisconsin | No | No | No | |||
256 | Fine scale stepwise q-scan: role of low-order rationales and resonance condition for ELM suppression | ELM Control | U of Wisconsin | No | No | No | |||
680 | Fine scale stepwise q-scan: role of low-order rationales and resonance condition for ELM suppression | ELM Control | U of Wisconsin | No | No | No | |||
619 | ELM divertor footprint and connection to ELM dynamics and effects of turbulence and modes | ELM Control | UCSD | No | No | No | |||
25 | Transport mechanisms induced by RMP | ELM Control | UCSD | No | No | Yes | |||
504 | Evolution of mitigation to suppression in RMP H-modes and Validation of nonlinear M3D simulations | ELM Control | UCSD | Yes | No | No | |||
505 | RMP ELM Control at ITER relevent rotation/torque | ELM Control | UCSD | No | 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 | |||
145 | Explore RMP ELM suppression mechanism at moderate collisionality | ELM Control | UCSD | No | 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 | |||
518 | Explore RMP ELM suppression mechanism at moderate collisionality | ELM Control | UCSD | No | No | No | |||
308 | RMP (Resonant Magnetic Perturbation) code validation via UCLA 288 GHz polarimeter | ELM Control | UCLA | No | No | No | |||
432 | Transport mechanisms induced by RMP | ELM Control | UCSD | No | 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 | |||
80 | Poloidal spectral measurements of n=3 RMP ELM suppression using the 3D magnetics upgrade | ELM Control | Department of Energy | 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 | |||
104 | Comparision of small-ELM regimes in DIII-D and NSTX | ELM Control | U of Wisconsin | 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 | |||
591 | Optimization of edge particle transport in ELM suppressed H-modes including high Z impurity control | 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 | |||
345 | Evaluating Physics of I-mode Stationary Enhanced Confinement Regime Without ELMs for the 2013 JR | ELM Control | LLNL | No | No | No | |||
453 | Minimize Density Pumpout During RMP ELM Suppression | ELM Control | LLNL | 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 | |||
343 | Evaluating Physics of RMP Stationary Enhanced Confinement Regime Without ELMs for the 2013 JRT | ELM Control | LLNL | No | No | Yes | |||
77 | Influence of rotation and rotation shear on ELM suppression | ELM Control | The college of William and Mary | Yes | No | No | |||
392 | Influence of rotation and rotation shear on ELM suppression | ELM Control | The college of William and Mary | No | 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 | |||
24 | Plasma response to 3D magnetic perturbations in the unfavorable grad-B drift direction | ELM Control | PPPL | Yes | No | No | |||
637 | RMP Effect on ELMs: Separate the effect of density pumpout | ELM Control | PPPL | No | No | No | |||
781 | Can RMP ELM Control be reliably used in ITER (or a reactor)? | ELM Control | PPPL | No | 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 | |||
101 | Investigation of n=1 RMP effects on ELMs with pitch-aligned configuration of I-coils | ELM Control | PPPL | Yes | Yes | Yes | |||
618 | Controlling VH-mode with RMPs and comparison to NSTX EPH-mode | ELM Control | PPPL | No | No | No | |||
755 | Heat flux footprint with pellet-paced ELMs vs nustar | ELM Control | PPPL | No | No | Yes | |||
629 | Transport study using Modulation RMP (M-RMP) | ELM Control | Zhejiang U | Yes | No | No | |||
126 | Triggering ELMs at high frequency with PPPL Lithium granule injector | ELM Control | Retired from PPPL | Yes | No | No | |||
454 | Synergy between core-localized Alfven eigenmodes and edge localized TBM fields on fast ion losses. | Energetic Particles | PPPL | No | Yes | No | |||
489 | Discussion of plasma rotation transient process during OFM/ELM-driven RWM w/wo feedback usin | Energetic Particles | PPPL | No | No | No | |||
130 | Synergy between core-localized Alfven eigenmodes and edge localized TBM fields on fast ion losses. | Energetic Particles | PPPL | No | Yes | No | |||
125 | Observation of non-linear interactions in fast-ion loss spectra | Energetic Particles | PPPL | No | No | No | |||
51 | Study of chirping Alfvén eigenmodes in DIII-D | Energetic Particles | PPPL | No | Yes | No | |||
52 | Control of TAE/RSAE modes via external perturbations | Energetic Particles | PPPL | No | No | No | |||
656 | Validating Critical Gradient Model for Burning Plasmas | Energetic Particles | PPPL | Yes | No | No | |||
703 | Use high betaP operating regime to study fast ion transport | Energetic Particles | LLNL | No | No | No | |||
592 | ECH Control of Alfven Eigenmodes | Energetic Particles | ITER Organization | Yes | Yes | 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 | |||
574 | Influence of non-axisymmetric fields (TBMs / RMPs) on fast ion confinement and loss | Energetic Particles | ITER Organization | Yes | No | Yes | |||
696 | Measure Change in 3D Field Induced EP Losses Due to Screening | 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 | |||
688 | Measure Beam Ion Transport due to Resonance Between Applied 3D Fields and Injected Beam Ion Orbits | Energetic Particles | GA | No | Yes | No | |||
612 | Investigate the Impact of ECH on Alfvenic Activity | Energetic Particles | GA | No | Yes | No | |||
82 | IR Imaging of I-coil Induced Fast Ion Losses | Energetic Particles | GA | No | Yes | No | |||
770 | Calibrated passive FIDA spectrum | Energetic Particles | UC, Irvine | No | No | No | |||
771 | Distribution function inversion benchmark | Energetic Particles | UC, Irvine | No | No | No | |||
38 | Calibrated passive FIDA spectrum | Energetic Particles | UC, Irvine | No | No | 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 | |||
525 | Test critical gradient model for fast-ion transport | Energetic Particles | UC, Irvine | No | No | No | |||
730 | Search for Fast Ion Critical Gradient | Energetic Particles | GA | No | No | No | |||
251 | New Study of Alfven Eigenmodes Induced Fast Ion Transport/Loss | Energetic Particles | GA | No | No | No | |||
384 | Run Coordinator Test Proposal II | General Physics | GA | No | No | No | |||
319 | Impact of fast-ions on the RWM stability boundary | General Physics | Columbia U | No | No | No | |||
304 | Birth of ITER: the world's largest resistor | General Physics | GA | No | No | No | |||
363 | TBM mockup simulating ITER GDC with ferritic materials | General Physics | GA | No | No | No | |||
365 | Lithium dropper commissioning and ELM modification | General Physics | GA | No | No | No | |||
259 | Helium Campaign (D beams) | General Physics | GA | No | No | No | |||
57 | Develop a high performance L-mode plasma. | General Physics | ORNL | Yes | No | No | |||
421 | Investigate Disagreements Between Thomson Scattering and ECE Measurements in High Te Discharges | General Physics | Massachusetts Institute of Technology | Yes | Yes | No | |||
383 | Run Coordinator Test Proposal | General Physics | LLNL | No | No | No | |||
456 | Energy Transport During Electron-Dominated Heating of ITER Baseline Scenario H-Mode Disch | Inductive Scenarios | PPPL | No | No | No | |||
61 | Energy Transport During Electron-Dominated Heating of ITER-Relevant H-Mode Discharges | Inductive Scenarios | PPPL | Yes | No | No | |||
41 | Investigation of the effects of the EHO toroidal mode number on the edge particle transport | Inductive Scenarios | PPPL | No | No | No | |||
511 | Impact of EHO on fast ion losses | Inductive Scenarios | PPPL | No | No | No | |||
573 | Impact of EHO on fast ion losses | Inductive Scenarios | PPPL | No | No | No | |||
344 | Evaluating Physics of QH-mode Stationary Enhanced Confinement Regime Without ELMs for the 2013 J | Inductive Scenarios | LLNL | No | No | No | |||
234 | Study fishbone-like instability at the edge of QH-modes | Inductive Scenarios | Instituto Superior Tecnico, Lisboa, Portugal | No | No | No | |||
404 | ITER Baseline Scenario Operation near the LH Threshold | Inductive Scenarios | ITER Organization | No | Yes | No | |||
415 | Access to zero torque advanced inductive with direct stabilization of the 2/1 mode by ECCD | Inductive Scenarios | ITER Organization | No | No | No | |||
416 | Burn Control in ITER Baseline Scenario | Inductive Scenarios | 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 | |||
789 | Iter Scenario: Optimize Radiative Divertor and Core Performance | Inductive Scenarios | PPPL | No | No | No | |||
638 | BetaN control with 3D Fields instead of NBI | Inductive Scenarios | PPPL | No | No | No | |||
784 | Understanding the NTM Stability Limits by q-profile modification | Inductive Scenarios | PPPL | No | No | No | |||
568 | ITER Baseline Scenario: Expand the operational limit by NTM stabilization and Time Dependent EFC | Inductive Scenarios | PPPL | No | No | No | |||
794 | ITER Scenario: Understanding the NTM Stability Limits by q-profile modification | Inductive Scenarios | PPPL | No | No | No | |||
124 | Electron Energy Transport during q0 control using modulated EC power | Inductive Scenarios | ORNL | No | No | No | |||
140 | q0 control with Counter-ECCD in ITER Baseline Discharges | Inductive Scenarios | Retired | No | No | No | |||
375 | QH-mode pedestal optimization | Inductive Scenarios | ORNL | No | No | No | |||
127 | Characterization of Intense Bursts of Millimeter Wave Emission in QH-mode Plasma | Inductive Scenarios | UC, Davis | Yes | No | No | |||
292 | Optimize electron pedestal pressure in low-torque ITER baseline plasmas | Inductive Scenarios | UCLA | No | No | No | |||
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 | |||
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 | |||
709 | Physics of EHO control in low-torque QH-mode | Inductive Scenarios | Department of Energy | No | No | No | |||
476 | Impact of TBM-induced field ripple in low-torque ITER baseline | Inductive Scenarios | Department of Energy | Yes | No | Yes | |||
628 | He H-mode plasmas studies for the ITER non-active operational phase | Inductive Scenarios | ITER Organization | Yes | No | Yes | |||
260 | ITER Baseline Scenario Demonstration | Inductive Scenarios | ITER Organization | No | Yes | No | |||
261 | Demonstration of stationary inductive solutions at low and moderate q95 | Inductive Scenarios | ITER Organization | No | No | No | |||
283 | ITER Baseline Scenario Operation near the LH Threshold | Inductive Scenarios | 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 | |||
471 | The experiment on generalized hybrid scenario with qmin > 2 at low density and relatively high q95 | Inductive Scenarios | ASIPP | Yes | No | No | |||
263 | Radiative divertor solutions in the ITER baseline scenario | Inductive Scenarios | ITER Organization | No | Yes | Yes | |||
411 | Demonstration of stationary inductive solutions at low and moderate q95 | Inductive Scenarios | ITER Organization | No | No | No | |||
418 | Mapping the current rise stability boundary for the ITER baseline scenario | Inductive Scenarios | ITER Organization | No | No | Yes | |||
419 | Support of ITER Research Plan for Q=10 Operation | Inductive Scenarios | ITER Organization | No | No | No | |||
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 | |||
681 | Transport Investigation During Slow Current Ramp-Up and Ramp-Down [for ITER] | Inductive Scenarios | U of Wisconsin | No | No | No | |||
257 | Transport Investigation During Slow Current Ramp-Up and Ramp-Down [for ITER] | Inductive Scenarios | U of Wisconsin | No | Yes | No | |||
246 | Develop low-torque, high normalized fusion performance QH-mode for ITER baseline scenario | Inductive Scenarios | GA | No | No | No | |||
247 | Develop low-torque, high normalized fusion performance QH-mode for FNSF-AT scenario | Inductive Scenarios | GA | No | No | No | |||
551 | Test compatibility of radiative divertor with QH-mode | Inductive Scenarios | GA | No | No | No | |||
534 | Develop low-torque, high normalized fusion performance QH-mode for ITER baseline scenario | Inductive Scenarios | GA | No | No | No | |||
527 | 256: SOL width and divertor peak heat flux in QH-mode plasmas with/without n=3 fields | Inductive Scenarios | GA | No | No | No | |||
243 | 256: SOL width and divertor peak heat flux in QH-mode plasmas with/without n=3 fields | Inductive Scenarios | GA | No | No | No | |||
10 | Maintain low-rotation QH-mode with ECH only | Inductive Scenarios | GA | No | No | No | |||
321 | Access to low torque QH-mode using high beta low torque AI target with NRMF | Inductive Scenarios | GA | No | No | No | |||
322 | ELM pacing in low torque, electron heated ITER baseline | Inductive Scenarios | GA | No | No | No | |||
323 | Access to QH-mode with low NBI torque | Inductive Scenarios | GA | No | No | No | |||
324 | Document turbulence change with rotation in AI, and compare with theory | Inductive Scenarios | GA | No | No | No | |||
337 | Routine current profile control in operation | Inductive Scenarios | GA | No | No | No | |||
589 | Exploration of super H-mode using high density QH-mode | Inductive Scenarios | GA | No | No | No | |||
645 | Access to low torque QH-mode using high beta low torque AI target with NRMF | Inductive Scenarios | GA | No | No | No | |||
652 | QH-mode operation with reduced divertor interaction | Inductive Scenarios | GA | No | No | No | |||
654 | Effect of sawteeth on QH-mode pedestal (EHO) | Inductive Scenarios | GA | No | No | No | |||
303 | Effect on lithium wall conditioning for Co-QH-mode and edge pedestal characteristics | Inductive Scenarios | GA | No | No | No | |||
490 | Maintain low-rotation QH-mode with ECH only | Inductive Scenarios | GA | No | No | No | |||
300 | Effect of triangularity in ITER shape and improved shaping | Inductive Scenarios | GA | No | No | No | |||
297 | ITER baseline scenario with low NBI torque | Inductive Scenarios | GA | No | No | No | |||
450 | Hybrids with co-NBI QH-mode edge | Inductive Scenarios | GA | No | No | No | |||
452 | Source of Magnetic Flux Pumping in Hybrids | Inductive Scenarios | GA | No | No | No | |||
313 | Hybrids with co-NBI QH-mode edge | Inductive Scenarios | GA | No | No | No | |||
494 | Further development of QH-mode with strong co-Ip NBI torque | Inductive Scenarios | GA | No | No | No | |||
495 | QH-mode with low torque start-up | Inductive Scenarios | GA | No | No | No | |||
13 | Compare edge particle transport in ELMing H-mode and QH-mode with and without NRMF | Inductive Scenarios | GA | No | No | No | |||
14 | Control of toroidal mode number of EHO | Inductive Scenarios | GA | No | No | No | |||
15 | Edge rotation shear threshold for QH-mode access | Inductive Scenarios | GA | No | No | No | |||
16 | Further development of QH-mode with strong co-Ip NBI torque | Inductive Scenarios | GA | No | No | No | |||
53 | QH-mode with low torque start-up | Inductive Scenarios | GA | No | No | No | |||
115 | QH-mode at low co-Ip torque using n=2 NRMF | Inductive Scenarios | GA | No | No | No | |||
120 | Optimizing non-resonant, nonaxisymmetric fields in QH-mode | Inductive Scenarios | GA | No | No | No | |||
118 | Dominant electron heated ITER baseline scenario studies | Inductive Scenarios | Columbia U | Yes | No | No | |||
497 | Cause(s) for the rotation degradation and tearing instabilities of the ITER baseline scenario | Inductive Scenarios | Columbia U | No | No | No | |||
318 | Current profile control for stable ITER baseline scenario plasmas | Inductive Scenarios | Columbia U | No | No | No | |||
266 | Understand resistive wall mode control physics in low-q95 plasmas | Inductive Scenarios | Columbia U | No | No | No | |||
604 | EF optimization of low-torque low-q95 QH mode plasmas | Inductive Scenarios | Columbia U | No | No | No | |||
330 | QH-mode with TBM | Inductive Scenarios | GA | No | No | No | |||
253 | Study QH-mode with advanced fast ion diagnostics and codes | Inductive Scenarios | GA | No | No | No | |||
194 | Correlation of confinement and fluctuations with electron heating in ITER Baseline Scenario | Inductive Scenarios | GA | No | No | No | |||
567 | Is loss of rotation in low-torque IBS discharges due to solenoid-related error fields? | Inductive Scenarios | GA | No | No | No | |||
444 | Identify the Optimal Impurity for High Power High Performance Plasmas During Radiating Divertor Ops | Inductive Scenarios | GA | No | No | No | |||
448 | Density Control and Active Impurity Removal from Double-null H-mode Plasmas | Inductive Scenarios | GA | No | No | No | |||
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 | |||
170 | Nature of Energy Released During H-L Back Transition | L-H Transition | GA | No | No | No | |||
678 | Understanding and Testing Methods for Producing Gentle HL Transitions | L-H Transition | GA | No | No | No | |||
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 | |||
307 | Role of turbulent-driven and Ion pressure gradient-sustained ExB flows in Triggering H-mode | L-H Transition | UCSD | No | No | No | |||
739 | Reduce L-H treshold power in H plasmas using pellet injection | L-H Transition | GA | No | No | Yes | |||
359 | q95 scaling of the coupled turbulence/zonal flow during LH transition | L-H Transition | U of Wisconsin | No | No | No | |||
360 | density scaling and X-point position scan of LH transition power threshold | L-H Transition | U of Wisconsin | No | No | No | |||
753 | q95 scaling of the coupled turbulence/zonal flow during LH transition | L-H Transition | U of Wisconsin | No | No | No | |||
754 | density scaling and X-point position scan of LH transition power threshold | L-H Transition | U of Wisconsin | No | No | No | |||
428 | Scaling of L-H transiton power with Xpoint location and collisionality | L-H Transition | UCSD | No | No | No | |||
28 | Role of profile evolution and energy transfer in L-H transition | L-H Transition | UCSD | No | No | No | |||
236 | Wavenumber dependence of turbulence suppression in the L-H transition | L-H Transition | UCLA | No | No | No | |||
2 | Hysteresis and Turbulence Spreading in the H-L Back Transition | L-H Transition | UCLA | No | No | No | |||
20 | L-H transition Trigger Physics/ Main Ion Momentum Balance | L-H Transition | UCLA | No | No | No | |||
706 | Physics of the low density branch of the L-H power threshold scaling | L-H Transition | UCLA | No | No | No | |||
707 | Physics of the low density branch of the L-H power threshold scaling | L-H Transition | UCLA | No | No | No | |||
750 | The role of non-local transport and avalanches in different L-H transition regimes | L-H Transition | UCLA | No | No | No | |||
670 | Investigate GAM's role in the L-H transition | L-H Transition | UCLA | No | No | No | |||
355 | q dependence of L-H transition power threshold | L-H Transition | UCLA | No | No | No | |||
346 | Control of H-L back transition via applied RMP fields | L-H Transition | UCLA | No | No | No | |||
672 | L-H threshold in hydrogen plasmas | L-H Transition | ORNL | No | No | No | |||
550 | Probing and controlling the L->H and H->L transitions by small pellet injection | L-H Transition | Korea Institute of Fusion Energy | No | No | No | |||
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 | |||
547 | Induced L-H-L transitions in IWL plasmas with applied n=1 C-coil | L-H Transition | PPPL | Yes | No | No | |||
376 | Role of q and magnetic shear of pedestal formation time and turbulent transport | Pedestal Structure | PPPL | No | No | No | |||
756 | QH-mode edge sweep with helium impurity for comparison to XGC0 | Pedestal Structure | PPPL | No | No | No | |||
71 | 4. ELM Characterization to Validate BOUT++ ELM Simulations | Pedestal Structure | LLNL | No | No | No | |||
510 | What can lost fast-ions tell us about the H-mode pedestal? | Pedestal Structure | PPPL | No | No | No | |||
745 | Transport studies in I-mode plasmas | Pedestal Structure | Massachusetts Institute of Technology | No | No | No | |||
751 | Dimensionless Identity Experiments in I-Mode with C-Mod and AUG (TC-18) | Pedestal Structure | Massachusetts Institute of Technology | No | Yes | No | |||
535 | Main-ion and impurity neoclassical flows compared with the PERFECT pedestal code | Pedestal Structure | Massachusetts Institute of Technology | No | No | Yes | |||
438 | Optimize electron pedestal pressure in ECH-heated QH-mode plasmas | Pedestal Structure | UCLA | No | No | No | |||
439 | Optimize electron pedestal pressure in ECH-heated QH-mode plasmas | Pedestal Structure | UCLA | No | No | No | |||
537 | Super H-Mode: Pedestal Evolution and Optimization | Pedestal Structure | ORNL | Yes | No | No | |||
556 | Pedestal optimization with RMP ELM Control | Pedestal Structure | ORNL | No | No | No | |||
372 | Pedestal optimization via impurity injection | Pedestal Structure | ORNL | No | No | No | |||
373 | Pedestal optimization in VH mode | Pedestal Structure | ORNL | No | No | No | |||
374 | Pedestal optimization with RMP ELM Control | Pedestal Structure | ORNL | No | No | No | |||
503 | Validation of M3D nonlinear MHD simulations of ELMs | Pedestal Structure | UCSD | Yes | No | No | |||
725 | What causes density buildup at the pedestal top? | Pedestal Structure | U of Wisconsin | No | No | No | |||
726 | Test Pedestal Structure Model Where Paleoclassical Transport Is Dominant | Pedestal Structure | U of Wisconsin | No | No | No | |||
262 | Test Pedestal Structure Model Where Paleoclassical Transport Is Dominant | Pedestal Structure | U of Wisconsin | No | No | No | |||
492 | Diagnostic spatial cross calibration using edge sweeps in QH-mode | Pedestal Structure | GA | No | No | No | |||
12 | Diagnostic spatial cross calibration using edge sweeps in QH-mode | Pedestal Structure | GA | No | No | No | |||
159 | Collisionality dependence of pedestal height with RMP | Pedestal Structure | GA | Yes | No | No | |||
579 | Mapping of Peeling Mode Stability Boundary | Pedestal Structure | GA | No | Yes | No | |||
370 | Particle pinch in pedestal | Pedestal Structure | GA | No | No | No | |||
729 | Dependence of pedestal structure on collisionality and Zeff in relation to JET results with ILW | Pedestal Structure | GA | No | Yes | No | |||
379 | Pedestal optimization of ITER baseline scenario discharges. | Pedestal Structure | GA | No | No | No | |||
665 | Feedback Control to Assess the Usefulness For Using Two Impurity Species in Radiating Divertor | Plasma Control | GA | No | No | No | |||
799 | Development for PID-controlled boundary radial field | Plasma Control | Consultant | No | No | No | |||
676 | Robust NTM control | Plasma Control | CRPP-EPFL | No | Yes | Yes | |||
695 | Poloidal rotation of plasma column to simulate rotating wall | Plasma Control | Columbia U | No | No | No | |||
776 | Control/Ops Evening Development Time | Plasma Control | GA | No | No | No | |||
773 | Model-based control of the current profile and βN for steady state scenarios | Plasma Control | GA | No | No | No | |||
802 | Breakdown Optimization with ECH | Plasma Control | GA | No | No | No | |||
524 | VFI bus voltage control and the True scaled ITER shape at DIII-D | Plasma Control | GA | No | No | No | |||
748 | Implement finite-state Off Normal Fault Response system | Plasma Control | GA | No | No | No | |||
252 | Implement finite-state Off Normal Fault Response system | Plasma Control | GA | No | No | No | |||
509 | Vertical positioning and stability control by means of reflectometry | Plasma Control | GA | No | No | No | |||
315 | Current profile control model requirements | Plasma Control | GA | No | No | No | |||
93 | Active Control of the EHO in Quiescent H-modes | Plasma Control | Department of Energy | Yes | No | No | |||
95 | Experimental Validation of a Revised PCS Error Field Category | Plasma Control | Department of Energy | No | No | No | |||
575 | Magnetic field limit for Glow Discharge wall cleaning | Plasma Control | ITER Organization | Yes | No | Yes | |||
316 | Model-based control of the current profile and βN for steady state scenarios | Plasma Control | Cadarache | No | No | No | |||
56 | Sawtooth Control | Plasma Control | ORNL | No | No | No | |||
369 | First-principles-driven Model-based Current-profile Control in H-mode Discharges | Plasma Control | Lehigh U | No | No | No | |||
758 | First-principles-driven Model-based Current Profile and Internal Energy Control in H-mode Discharges | Plasma Control | Lehigh U | No | No | No | |||
796 | Snowflake Control | Plasma Control | PPPL | No | No | No | |||
797 | BetaN control with 3D Coils | Plasma Control | PPPL | No | No | No | |||
791 | Detachment Control for H-mode | Plasma Control | PPPL | No | No | No | |||
792 | Combined Core and Divertor Radiation Control: Gas Injection Feedback with Radiation Measurements | Plasma Control | PPPL | No | No | No | |||
793 | qmin control | Plasma Control | PPPL | No | No | No | |||
782 | RMP ELM Control Development | Plasma Control | PPPL | No | No | No | |||
766 | Island seeding with saw teeth pacing: New method to control tearing modes | Plasma Control | PPPL | No | No | No | |||
201 | NTM Control Upgrade: Capibility to deposit EC at multiple locations | Plasma Control | PPPL | Yes | No | No | |||
719 | NTM Control Upgrade: Capibility to deposit EC at multiple locations | Plasma Control | PPPL | No | No | No | |||
720 | Real-time Error Field Correction | Plasma Control | PPPL | No | No | No | |||
722 | NTM control with ECCD, Real-time Ray Tracing and real-time Mirrors | Plasma Control | PPPL | No | No | No | |||
566 | Testing of New Hardware and Software Capabilities for NTM Control | Plasma Control | PPPL | No | No | No | |||
213 | Real-time Ray Tracing for PCS | Plasma Control | PPPL | Yes | No | No | |||
156 | Controlling the timing and evolution of L-H and H-L with 3D fields | Plasma Control | PPPL | Yes | No | No | |||
211 | Control of experimentally simulated burning state | Plasma Control | QST | Yes | No | 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 | |||
395 | Rotation reversal | Plasma Rotation | The college of William and Mary | No | No | 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 | |||
327 | rho* scaling of intrinsic torque between DIII-D and JET | Plasma Rotation | GA | No | Yes | 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 | |||
423 | Coupling of multi-channel transport and turbulence across rotation reversals | Plasma Rotation | Massachusetts Institute of Technology | Yes | Yes | No | |||
391 | Current/Density Scaling of Intrinsic Rotation and ITG/TEM Transition | Plasma Rotation | UCLA | No | No | No | |||
47 | Quantifying the TBM torque, both in magnitude and radial location | Plasma Rotation | VTT Technical Research Centre | No | No | No | |||
48 | Dependence of momentum transport and intrinsic torque on rho* and beta | Plasma Rotation | VTT Technical Research Centre | No | Yes | No | |||
460 | Quantifying the TBM torque, both in magnitude and radial location | Plasma Rotation | VTT Technical Research Centre | No | No | Yes | |||
461 | Dependence of momentum transport and intrinsic torque on rho* and beta | Plasma Rotation | VTT Technical Research Centre | No | Yes | No | |||
350 | Current/Density Scaling of Intrinsic Rotation and ITG/TEM Transition | Plasma Rotation | UCLA | No | No | No | |||
426 | Investigate the role of RS on inward momentum transport | Plasma Rotation | UCSD | No | No | No | |||
427 | Collisionality dependence of intrinsic rotation | Plasma Rotation | UCSD | No | No | No | |||
429 | Investigate the role of RS on inward momentum transport | Plasma Rotation | UCSD | No | No | No | |||
433 | Investigate the role of RS on inward momentum transport | Plasma Rotation | UCSD | No | No | No | |||
290 | Effect of n=2 Poloidal Spectrum on NTV Torque | Plasma Rotation | Department of Energy | No | No | No | |||
646 | rho* scaling of intrinsic torque between DIII-D and JET | Plasma Rotation | GA | No | Yes | No | |||
560 | NBI Driven Poloidal Rotation | Plasma Rotation | GA | No | No | No | |||
210 | The Dependence of Poloidal Rotation on Turbulence | Plasma Rotation | GA | No | No | No | |||
244 | Study NRMF driven torque in ECH-only heated plasma (ELMing H-modes) | Plasma Rotation | GA | No | No | No | |||
386 | Measure Intrinsic Rotation Size scaling in DIII-D alone -II | Plasma Rotation | GA | No | No | No | |||
11 | Investigate in-out density asymmetry at large toroidal rotation | Plasma Rotation | GA | No | No | No | |||
4 | Turbulence and Intrinsic Rotation | Plasma Rotation | GA | No | No | No | |||
5 | Measure Intrinsic Rotation Size scaling in DIII-D alone -II | Plasma Rotation | GA | No | No | No | |||
258 | Main-ion and impurity rotation in helium plasmas | Plasma Rotation | GA | No | No | No | |||
528 | Study NRMF driven torque in ECH-only heated plasma (ELMing H-modes) | Plasma Rotation | GA | No | No | No | |||
491 | Investigate in-out density asymmetry at large toroidal rotation | Plasma Rotation | GA | No | No | No | |||
488 | Investigate angular momentum diffusion and pinch using off-axis torque | Plasma Rotation | GA | No | No | No | |||
6 | Prompt torque and zonal flow damping | Plasma Rotation | GA | No | No | No | |||
7 | Investigate angular momentum diffusion and pinch using off-axis torque | Plasma Rotation | GA | No | No | No | |||
8 | Compare Mach probe and CER measurements of intrinsic rotation profile of main ions in helium plasma | Plasma Rotation | GA | No | No | No | |||
9 | Test of Neoclassical Toroidal Viscosity theory using modulated I-coil currents | Plasma Rotation | GA | No | No | No | |||
407 | n-scaling of magnetic errors (TBM related) | Plasma Rotation | GA | No | No | Yes | |||
697 | Electromagnetic Torque Waves â?? Transport of Angular Momentum | Plasma Rotation | Columbia U | No | 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 | |||
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 | |||
279 | ECH effects on low or balanced torque discharges in DIII-D | Plasma Rotation | National Fusion Research Institute (NFRI), Korea | Yes | Yes | No | |||
280 | : Trigger-less onset of NTMs with PEC and NTV effects on rotation regime | Plasma Rotation | Istituto di Fisica del Plasma, Euratom-ENEA-CNR | No | No | 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 | |||
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 | |||
795 | Measure NTV torque profile | Plasma Rotation | Columbia U | No | No | No | |||
662 | NTV Collisionality Regime Test | Plasma Rotation | Columbia U | No | No | No | |||
1 | C vs I Coil NTV | Plasma Rotation | GA | No | No | No | |||
653 | High-Z Transport in QH-mode Plasmas | Plasma-material Interface | GA | No | No | No | |||
241 | C-13 and background carbon | Plasma-material Interface | GA | No | No | No | |||
233 | C erosion and D up-take at high surface temperature | Plasma-material Interface | GA | No | No | No | |||
601 | Control of tungsten PFC erosion by local gas injection | Plasma-material Interface | GA | No | No | No | |||
89 | Mo, W, Al, Be DiMES net/gross erosion experiments | Plasma-material Interface | U of Toronto | Yes | Yes | 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 | |||
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 | |||
474 | 3D material migration during RMP ELM suppression | Plasma-material Interface | U of Wisconsin | Yes | Yes | No | |||
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 | |||
206 | Studies of arcing on divertor PFC surfaces | Plasma-material Interface | UCSD | No | No | No | |||
207 | Dust generation from deposited layers and leading edges | Plasma-material Interface | UCSD | No | No | No | |||
215 | Control of tungsten PFC erosion by local gas injection | Plasma-material Interface | UCSD | No | No | No | |||
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 | |||
530 | Studies of arcing on divertor PFC surfaces | Plasma-material Interface | UCSD | No | No | No | |||
531 | Dust generation from deposited layers and leading edges | Plasma-material Interface | UCSD | No | No | No | |||
543 | Control of high-Z PFC erosion by local gas injection | Plasma-material Interface | UCSD | Yes | No | No | |||
734 | First wall heat flux and erosion due to TBM induced error fields | Plasma-material Interface | ORNL | No | No | No | |||
368 | Investigation of extreme outer wall heating caused by the DIII-D TBM | Plasma-material Interface | LLNL | No | Yes | Yes | |||
128 | Carbon-13 in He Plasma erosion/deposition experiment to benchmark DIVIMP code being used by ITER | Plasma-material Interface | Commonwealth Fusion Systems | No | No | No | |||
90 | Carbon-13 in He Plasma erosion/deposition experiment to benchmark DIVIMP code being used by ITER | Plasma-material Interface | Commonwealth Fusion Systems | No | No | No | |||
736 | Erosion/Deposition of Aluminum with low density He L-mode Simple-As-Possible Plasmas | Plasma-material Interface | Commonwealth Fusion Systems | No | No | No | |||
231 | Stabilization of NTMs with ECCD | Stability & Disruption Avoidance | QST | No | Yes | No | |||
291 | Trigger-less onset of NTMs with P_EC and NTV effects on rotation regime | Stability & Disruption Avoidance | Instituto Superior Tecnico, Lisboa, Portugal | No | No | No | |||
785 | Active determination of angular momentum transfer process between 3D structures: NTM 2/1 and 3/2 mo | Stability & Disruption Avoidance | PPPL | No | No | No | |||
329 | Discussion of plasma rotation transient process during OFM/ELM-driven RWM w/wo feedback usin | Stability & Disruption Avoidance | PPPL | No | No | No | |||
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 | |||
565 | Benign 3/2 NTM Formation to avoid 2/1 NTM locking | Stability & Disruption Avoidance | PPPL | No | 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 | |||
212 | Island seeding with saw teeth pacing: New method to control tearing modes | Stability & Disruption Avoidance | PPPL | Yes | No | No | |||
562 | RMP NTM interaction | Stability & Disruption Avoidance | PPPL | Yes | No | No | |||
320 | RWM excitation in the SSI target by reducing triangularity" | Stability & Disruption Avoidance | PPPL | No | No | No | |||
737 | n=1 and n=2 simultaneous DEFC /DFB for routine demonstration of low q << 2 RWM stable regime | Stability & Disruption Avoidance | PPPL | No | No | No | |||
738 | The investigation of EP-kinetic effects and plasma rotation with low q and low beta operation | Stability & Disruption Avoidance | PPPL | No | No | No | |||
578 | Â N=2 mode rotation technique development using the current-driven loq q RWM onset | Stability & Disruption Avoidance | PPPL | Yes | No | Yes | |||
122 | Bid farewell to locked modes - NTM-locking avoidance by feedback synchronization assisted with ECCD | Stability & Disruption Avoidance | PPPL | Yes | No | No | |||
123 | Bid farewell to locked modes - NTM-locking avoidance by feedback synchronization assisted with ECCD | Stability & Disruption Avoidance | PPPL | No | No | No | |||
163 | Exploration of DEFC in the feedback stabilized plasma in low-q discharges | Stability & Disruption Avoidance | PPPL | Yes | No | No | |||
174 | Exploration of DEFC in the feedback stabilized plasma in low-q discharges | Stability & Disruption Avoidance | PPPL | No | No | No | |||
762 | ITER Baseline Scenario: Expand the operational limit by NTM stabilization and Time Dependent EFC | Stability & Disruption Avoidance | PPPL | No | No | No | |||
763 | Expand the high li, betaN >4 operating regime through NTM Stabilization | Stability & Disruption Avoidance | PPPL | No | No | No | |||
764 | Multiple periods of NTM suppression | Stability & Disruption Avoidance | PPPL | No | No | No | |||
765 | Island seeding with saw teeth pacing: New method to control tearing modes | Stability & Disruption Avoidance | PPPL | No | No | No | |||
202 | Error Field Correction Improvement: Adding BetaN dependence | Stability & Disruption Avoidance | PPPL | Yes | No | No | |||
718 | Compare the power threshold for pre-emptive NTM suppression vs Catch and Subdue | Stability & Disruption Avoidance | PPPL | No | No | No | |||
217 | PID (proportional integral derivative)control of Error Field | Stability & Disruption Avoidance | PPPL | Yes | No | No | |||
760 | Marginal 2/1 island width in IBS | Stability & Disruption Avoidance | Retired from GA | No | No | No | |||
425 | Flow or flow shear for m/n=2/1 tearing mode stabilization? | Stability & Disruption Avoidance | Retired from GA | Yes | Yes | 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 | |||
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 | |||
622 | Identification of entrainment threshold in I-coil amplitude/frequency space | Stability & Disruption Avoidance | Massachusetts Institute of Technology | Yes | No | No | |||
602 | Rotating field current drive for NTM suppression | Stability & Disruption Avoidance | Massachusetts Institute of Technology | Yes | No | No | |||
451 | Disruption mitigation by differential rotation of internal MHD | Stability & Disruption Avoidance | Los Alamos National Laboratory | Yes | No | No | |||
328 | Error field correction at low rotation | Stability & Disruption Avoidance | GA | No | No | No | |||
317 | Study on sawteeth in the neutral beam (NB) heated plasmas | Stability & Disruption Avoidance | Korea National Fusion Research Center | No | No | No | |||
741 | Quantifying the improved confinement achieved by NTM spinup | Stability & Disruption Avoidance | Massachusetts Institute of Technology | No | No | No | |||
742 | Measurement of viscous torque on locked 2/1 mode | Stability & Disruption Avoidance | Massachusetts Institute of Technology | No | No | No | |||
743 | Measurement of viscous torque on locked 2/1 mode | Stability & Disruption Avoidance | Massachusetts Institute of Technology | No | No | No | |||
744 | NBI torque assisted unlocking and spinup experiments | Stability & Disruption Avoidance | Massachusetts Institute of Technology | No | No | No | |||
232 | Bifurcated helical core equilibrium - continued | Stability & Disruption Avoidance | U of Wisconsin | 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 | |||
458 | Test optimized TBM error field correction at higher values of beta | Stability & Disruption Avoidance | CRPP-EPFL | No | No | 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 | |||
96 | Effect of Error Field Control Currents on Strike Point Splitting | Stability & Disruption Avoidance | Department of Energy | No | No | No | |||
498 | Validation of single-mode model of error field correction for n=2 fields | Stability & Disruption Avoidance | Department of Energy | Yes | Yes | No | |||
499 | Up/down Asymmetric EFC | Stability & Disruption Avoidance | Department of Energy | No | No | No | |||
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 | |||
366 | Up/down Asymmetric EFC | Stability & Disruption Avoidance | Department of Energy | No | No | No | |||
102 | TBM mock-up effects on confinement at high β | Stability & Disruption Avoidance | ITER Organization | Yes | No | Yes | |||
455 | TBM mock-up effects on confinement at high β | Stability & Disruption Avoidance | ITER Organization | 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 | |||
626 | Validation of ECCD NTM stabilization criteria | Stability & Disruption Avoidance | ITER Organization | Yes | No | Yes | |||
326 | Understand mechanisms by which ECH influences NTM stablility | Stability & Disruption Avoidance | GA | No | No | No | |||
675 | Error field correction at low rotation | Stability & Disruption Avoidance | GA | No | Yes | No | |||
657 | Initial n=2 error field correction | Stability & Disruption Avoidance | GA | No | No | No | |||
658 | Plasma response to n=2 perturbations | Stability & Disruption Avoidance | GA | No | No | No | |||
659 | n = 2 Dynamic Error Field Correction | Stability & Disruption Avoidance | GA | No | No | No | |||
660 | Dependence of non-axisymmetric plasma response on plasma rotation | Stability & Disruption Avoidance | GA | No | No | No | |||
526 | q95 < 2 Tokamak Operation Via Dynamic Error Field Correction | Stability & Disruption Avoidance | GA | No | No | No | |||
442 | Measurement of Inductive Poloidal Current | Stability & Disruption Avoidance | GA | No | No | No | |||
242 | q95 < 2 Tokamak Operation Via Dynamic Error Field Correction | Stability & Disruption Avoidance | GA | No | No | No | |||
309 | Full 3D Rotation optimization of H mode | Stability & Disruption Avoidance | GA | No | Yes | Yes | |||
298 | Soft landing with 2/1 TM in the ITER shape | Stability & Disruption Avoidance | GA | No | No | No | |||
445 | Effect of Islands on ECCD | Stability & Disruption Avoidance | GA | No | No | No | |||
60 | Effective NTM control in low torque plasmas | Stability & Disruption Avoidance | GA | No | No | No | |||
331 | QH-mode with TBM (dup 330) | Stability & Disruption Avoidance | GA | No | No | No | |||
354 | Control of Major Disruptions in DIII-D | Stability & Disruption Avoidance | Columbia U | No | 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 | |||
500 | q95<2 tokamak operation via dynamic error field correction | Stability & Disruption Avoidance | Consorzio RFX | Yes | No | No | |||
105 | Optimization and exploration of the q95<2 scenario in DIII-D | Stability & Disruption Avoidance | Consorzio RFX | 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 | |||
361 | Dither injection for closed-loop system identification of vacuum and plasma response | Stability & Disruption Avoidance | Consultant | No | No | No | |||
698 | Dither injection for closed-loop system identification of vacuum and plasma response | Stability & Disruption Avoidance | Consultant | No | No | No | |||
699 | Feedback control of mode rotation and phase | Stability & Disruption Avoidance | Consultant | No | No | No | |||
700 | PID-controlled boundary radial field for â??spontaneousâ?? mode-unlocking | Stability & Disruption Avoidance | Consultant | No | No | No | |||
663 | Effect of higher mode number error fields on n=1 Locking Threshold | Stability & Disruption Avoidance | Columbia U | No | No | No | |||
617 | Characterization of core/pedestal density limits for rotating tearing modes | Stability & Disruption Avoidance | Columbia U | No | No | 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 | |||
605 | Importance of matched poloidal spectra in most sensitive EFC conditions | Stability & Disruption Avoidance | Columbia U | No | No | No | |||
606 | Dominant kink-mode poloidal coupling dependence with betaN, q95 | Stability & Disruption Avoidance | Columbia U | No | No | No | |||
607 | Direct measurement of E-coil contribution to intrinsic EF | Stability & Disruption Avoidance | Columbia U | No | No | No | |||
610 | Local correction of the TBM error field | Stability & Disruption Avoidance | Columbia U | No | No | No | |||
611 | Absolute plasma response null measurement by multiple betaN steps | Stability & Disruption Avoidance | Columbia U | No | No | No | |||
338 | Local correction of the TBM error field | Stability & Disruption Avoidance | Columbia U | No | No | Yes | |||
364 | Absolute plasma response null measurement by multiple betaN steps | Stability & Disruption Avoidance | Columbia U | No | 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 | |||
188 | Extension of proxy error field experiments to H-mode plasmas | Stability & Disruption Avoidance | Columbia U | No | No | No | |||
496 | Impact of fast-ions on the RWM stability boundary | Stability & Disruption Avoidance | Columbia U | No | No | No | |||
740 | Respond to locking by ramping IP down | Stability & Disruption Avoidance | Columbia U | No | No | No | |||
119 | Impact of fast-ions on the RWM stability boundary | Stability & Disruption Avoidance | Columbia U | Yes | Yes | No | |||
85 | Current profile control for stable ITER baseline scenario plasmas | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |||
757 | Cause(s) for the rotation degradation and tearing instabilities of the ITER baseline scenario | Stability & Disruption Avoidance | Columbia U | No | No | No | |||
296 | Determine dependence of RWM marginal stability on rotation and energetic particles | Stability & Disruption Avoidance | Columbia U | Yes | Yes | Yes | |||
549 | Testing kinetic RWM stabilization theory at marginal stability in high beta, TM stabilized plasmas | Stability & Disruption Avoidance | Columbia U | Yes | Yes | Yes | |||
705 | Develop feedback-controlled 3D equilibria | Stability & Disruption Avoidance | Columbia U | No | No | No | |||
636 | Time-resolved measurement of plasma response spectrum | Stability & Disruption Avoidance | Columbia U | No | No | No | |||
759 | Link between driven plasma response and tearing stability | Stability & Disruption Avoidance | Columbia U | No | No | No | |||
710 | RWM control using external coils | Stability & Disruption Avoidance | Columbia U | No | 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 | |||
685 | Locked mode control at low (ITER-like) q95 and with external C-coils | Stability & Disruption Avoidance | Columbia U | No | No | No | |||
686 | â??Born-lockedâ?? mode control by ECCD and magnetic perturbations | Stability & Disruption Avoidance | Columbia U | No | No | No | |||
687 | Add modulated ECCD to f/back or f/fwd entrainment discharges | Stability & Disruption Avoidance | Columbia U | No | No | No | |||
633 | Plasma response to small applied rotating fields as an error-field-detection method | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |||
689 | Assess optimal Error Field Correction by modulating I-coils at incommensurable frequencies | Stability & Disruption Avoidance | Columbia U | No | No | No | |||
690 | EFC by ramping beta up or q95 down or NBI torque down (instead of density down) in 3-4 discharges | Stability & Disruption Avoidance | Columbia U | No | No | No | |||
691 | Locked-mode avoidance by magnetic f/back on saddle-loops | Stability & Disruption Avoidance | Columbia U | No | No | No | |||
692 | NTMs â??on demandâ??, by ECH | Stability & Disruption Avoidance | Columbia U | No | No | No | |||
693 | NTMs â??on demandâ??, by modulated ECCD | Stability & Disruption Avoidance | Columbia U | No | No | No | |||
677 | Robust NTM control | Stability & Disruption Avoidance | CRPP-EPFL | No | Yes | Yes | |||
570 | Space, time and energy-resolved x-ray measurements for magnetically confined fusion plasmas | Stability & Disruption Avoidance | PPPL | Yes | No | No | |||
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 | |||
267 | Understand and control resistive wall mode stability in high-qmin plasmas | Steady State Heating and Current Drive | Columbia U | No | No | No | |||
30 | New Optimal Plasma Shape for AT Scenario? | Steady State Heating and Current Drive | GA | No | No | No | |||
569 | High Beta, Steady State Hybrids | Steady State Heating and Current Drive | GA | 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 | |||
32 | High Beta Hybrids and Pressure Profile Broadening | Steady State Heating and Current Drive | GA | No | No | No | |||
33 | High Beta, Steady State Hybrids | Steady State Heating and Current Drive | GA | No | No | No | |||
708 | 444: Identify the Optimal Impurity for High Power High Performance Plasmas During Radiating Divertor Ops | Steady State Heating and Current Drive | GA | No | No | No | |||
42 | Compatibility of High Performance Plasmas With a Puff-and-Pump Radiating Divertor | Steady State Heating and Current Drive | GA | No | No | No | |||
36 | Natural ELM Pacing in High-Beta, Steady-State Plasmas | Steady State Heating and Current Drive | GA | No | No | No | |||
436 | High Beta Hybrids and Pressure Profile Broadening | Steady State Heating and Current Drive | GA | Yes | No | No | |||
521 | Dependence of confinement and stability on toroidal rotation in high li discharges | Steady State Heating and Current Drive | GA | No | No | No | |||
536 | Low rotation, elevated q_min steady-state scenario discharges at high betaN and 210R MSE | Steady State Heating and Current Drive | GA | No | No | No | |||
539 | Produce fNI = 1 discharges at q_min near 1.5 using off-axis injection and a model guided approach | Steady State Heating and Current Drive | GA | No | No | No | |||
540 | Establish the incremental confinement of EC power in high betaN steady-state scenario discharges | Steady State Heating and Current Drive | GA | No | No | No | |||
548 | Improve the optimized high li operating regime through 1/1 and 2/1 instability avoidance | Steady State Heating and Current Drive | GA | No | No | No | |||
554 | The impact of increased pressure gradient on scenarios for fully noninductive operation | Steady State Heating and Current Drive | GA | No | No | No | |||
613 | Testing for parameter space with the best fast ion confinement at high q_min | Steady State Heating and Current Drive | GA | No | No | No | |||
158 | Expand the high li, betaN >4 operating regime through instability avoidance and higher heating power | Steady State Heating and Current Drive | GA | No | No | No | |||
160 | Dependence of confinement and stability on toroidal rotation in high li discharges | Steady State Heating and Current Drive | GA | No | No | No | |||
164 | Produce fNI = 1 discharges at q_min near 1.5 using off-axis injection and a model guided approach | Steady State Heating and Current Drive | GA | No | No | No | |||
172 | High betaN with off-axis injection at reduced Bt (if 2011-level beam power is available) | Steady State Heating and Current Drive | GA | No | No | No | |||
173 | Confinement and fast ion diffusion in high betaN, steady-state scenario discharges | Steady State Heating and Current Drive | GA | No | No | No | |||
162 | 210RT MSE and low rotation, elevated q_min steady-state scenario discharges at high betaN | Steady State Heating and Current Drive | GA | No | No | No | |||
178 | Beta limit and bootstrap current fraction in ITER steady-state scenario discharges | Steady State Heating and Current Drive | GA | No | No | No | |||
180 | Establish the incremental confinement of EC power in high betaN steady-state scenario discharges | Steady State Heating and Current Drive | GA | No | No | No | |||
716 | Assess the destabilization mechanism for the n = 1 tearing mode in steady-state scenario discharges | Steady State Heating and Current Drive | GA | No | No | No | |||
783 | Development of Fully Noninductive High Beta EAST Scenario II | Steady State Heating and Current Drive | GA | No | No | No | |||
545 | High beta with NCS and qmin>2 | Steady State Heating and Current Drive | GA | No | No | No | |||
312 | Limits to pedestal radiation high beta discharges | Steady State Heating and Current Drive | GA | No | No | No | |||
249 | Steady-state high beta with NCS and qmin>2 | Steady State Heating and Current Drive | GA | No | No | No | |||
615 | Increase achievable betaN in high betaP experiment using n=3 betaN feedback (ala burn control) | Steady State Heating and Current Drive | GA | No | No | No | |||
336 | Routine current profile control in operation | Steady State Heating and Current Drive | GA | No | No | No | |||
289 | Demonstrate access to beta_N=5 with min(q)>2 | Steady State Heating and Current Drive | ITER Organization | No | No | No | |||
412 | Development of Reproducible Startup and Target q Profile Control for Steady State Scenarios | Steady State Heating and Current Drive | ITER Organization | No | No | No | |||
413 | Demonstrate access to beta_N=5 with min(q)>2 | Steady State Heating and Current Drive | ITER Organization | No | No | No | |||
414 | High li steady-state scenario development | Steady State Heating and Current Drive | ITER Organization | No | No | No | |||
287 | High li steady-state scenario development | Steady State Heating and Current Drive | ITER Organization | No | No | No | |||
284 | Access conditions for steady-state operation in ITER | Steady State Heating and Current Drive | ITER Organization | No | Yes | No | |||
470 | Development of Fully Noninductive High Beta EAST Scenario | Steady State Heating and Current Drive | ASIPP | Yes | No | No | |||
459 | Model-based control of the current profile and βN for steady state scenarios | Steady State Heating and Current Drive | Cadarache | No | No | No | |||
774 | Rotating Magnetic Field Current Drive (RMFCD) | Steady State Heating and Current Drive | Massachusetts Institute of Technology | No | No | No | |||
595 | ITER steady-state scenario in USN, +BT | Steady State Heating and Current Drive | ORNL | No | No | No | |||
596 | q95 dependency of beam ion confinement in high qmin scenario | Steady State Heating and Current Drive | ORNL | No | No | No | |||
597 | Apple-to-apple comparison of ITER steady-state scenarios: high/elevated qmin, SS hybrid, and high li | Steady State Heating and Current Drive | ORNL | No | No | No | |||
598 | Far off-axis NBCD using vertically shifted plasma | Steady State Heating and Current Drive | ORNL | No | No | No | |||
599 | Measurement of neoclassical response of off-axis beam ions | Steady State Heating and Current Drive | ORNL | No | No | No | |||
600 | Anomalous current diffusion in steady-state hybrid scenario with ELM suppression | Steady State Heating and Current Drive | ORNL | No | No | No | |||
332 | Demonstration of noninductive Q=5 scenario in ITER shape using off-axis NBI | Steady State Heating and Current Drive | ORNL | No | No | No | |||
333 | Far off-axis NBCD | Steady State Heating and Current Drive | ORNL | No | No | No | |||
334 | Measurement of neoclassical response of off-axis beam ions | Steady State Heating and Current Drive | ORNL | No | No | No | |||
335 | Off-axis NBCD measurement in steady state scenario | Steady State Heating and Current Drive | ORNL | No | No | No | |||
382 | Transport and turbulence characterization experiment | Steady State Heating and Current Drive | UCLA | No | No | No | |||
151 | ITER SS Demo Discharge Documentations | Steady State Heating and Current Drive | Retired | No | No | No | |||
544 | Super H-Mode: Scenario Development | Steady State Heating and Current Drive | ORNL | Yes | No | No | |||
39 | Measure and understand energetic particle profiles in steady-state plasmas | Steady State Heating and Current Drive | UC, Irvine | No | No | No | |||
664 | Follow-up studies of fast-ion transport effects on steady-state plasmas | Steady State Heating and Current Drive | UC, Irvine | No | No | No | |||
787 | Optimize Radiative Divertor and Core Performance | Steady State Heating and Current Drive | PPPL | No | No | No | |||
643 | Campaign to study physics at the Greenwald limit | Steady State Heating and Current Drive | PPPL | No | No | No | |||
780 | 3D coil based BetaN control instead of NBI based BetaN control. | Steady State Heating and Current Drive | PPPL | No | No | No | |||
721 | qmin control | Steady State Heating and Current Drive | PPPL | No | No | No | |||
175 | Beta collapse avoidance in SSI discharges by de-synchronizing toroidal harmonics by using feedback | Steady State Heating and Current Drive | PPPL | No | No | No | |||
176 | Beta collapse avoidance in SSI discharges by de-synchronizing toroidal harmonics by using feedback | Steady State Heating and Current Drive | PPPL | No | No | No | |||
138 | SSI target improvement by minimizing global low-n MHD activity in 1.5 Steady State Heating and Current Drive | PPPL | No | 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 | |||
208 | qmin control | Steady State Heating and Current Drive | PPPL | Yes | No | No | |||
216 | Campaign to study physics at the Greenwald limit | Steady State Heating and Current Drive | PPPL | Yes | No | No | |||
310 | Energy Transport During Electron-Dominated Heating of ITER-Relevant H-Mode Discharges | Steady State Heating and Current Drive | PPPL | No | No | No | |||
501 | Energy Transport During Electron-Dominated Heating of ITER Baseline Scenario H-Mode Discharges | Steady State Heating and Current Drive | PPPL | No | No | 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 | |||
179 | Snowflake in AT Plasma | Steady State Heating and Current Drive | LLNL | No | No | No | |||
704 | Use high betaP operating regime to study fast ion transport | Steady State Heating and Current Drive | LLNL | No | No | No | |||
775 | High qmin transient betaN=5 demonstration | Steady State Heating and Current Drive | LLNL | No | No | No | |||
538 | Reduce fast ion transport in high qmin, high beta plasmas | Steady State Heating and Current Drive | LLNL | No | No | No | |||
311 | Transport with qmin>2 | Steady State Heating and Current Drive | LLNL | No | No | No | |||
209 | RMP ELM-Control for Snowflake Configurations | Torkil Jensen Award | LLNL | Yes | No | No | |||
214 | Density (Greenwald) Limit and the Radiation Driven Islands | Torkil Jensen Award | PPPL | Yes | No | No | |||
557 | Density (Greenwald) Limit and the Radiation Driven Islands | Torkil Jensen Award | PPPL | Yes | No | No | |||
650 | ELM Mitigation with ECCD | Torkil Jensen Award | PPPL | No | No | No | |||
255 | Super H-Mode | Torkil Jensen Award | ORNL | Yes | No | No | |||
640 | Fully Non-Inductive, Low Rotation QH-mode | Torkil Jensen Award | ORNL | No | No | No | |||
761 | Rotating Magnetic Field Current-Drive (RMFCD) | Torkil Jensen Award | Massachusetts Institute of Technology | No | No | No | |||
800 | Physics of EHO control in low-torque QH-mode | Torkil Jensen Award | Department of Energy | No | No | No | |||
546 | Investigate elongation limit in low li discharges with/without applied 3D magnetic fields | Torkil Jensen Award | GA | No | No | No | |||
248 | Investigate elongation limit in low li discharges with/without applied 3D magnetic fields | Torkil Jensen Award | GA | No | No | No | |||
529 | Investigate the physics of NTM suppression by large externally applied helical fields | Torkil Jensen Award | GA | No | No | No | |||
245 | Investigate the physics of NTM suppression by large externally applied helical fields | Torkil Jensen Award | GA | No | No | No | |||
204 | Suppression of Density Limit Disruptions with RMP Fields | Torkil Jensen Award | GA | No | No | 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 | |||
507 | Exploring Impurity Density Asymmetries due to NBI Fast Ions and Their Effect on Impurity Transport | Torkil Jensen Award | _ | No | No | No | |||
514 | LOC/SOC Studies | Turbulence & Transport | MIT PSFC | Yes | Yes | No | |||
299 | Aspect ratio scaling of turbulence and transport: DIII-D and NSTX-U comparison | Turbulence & Transport | Univ. Wisconsin (at PPPL) | No | No | No | |||
593 | Demonstrating Stiffness of Electron Heat Transport in the Presence of Strong Radiation | Turbulence & Transport | Massachusetts Institute of Technology | No | No | No | |||
268 | nu* dimensionless scaling | Turbulence & Transport | CEA | No | Yes | No | |||
34 | Electron Critical Gradient and Heat Pinch | Turbulence & Transport | GA | No | No | No | |||
35 | Non-Diffusive Heat Fluxes in the Edge "Shortfall" Region | Turbulence & Transport | GA | No | No | No | |||
31 | Test of Turbulence Spreading Using Turbulence Propagation | Turbulence & Transport | GA | No | No | No | |||
195 | Correlation of confinement and fluctuations with electron heating in ITER Baseline Scenario | Turbulence & Transport | GA | No | No | No | |||
152 | Transport shortfall at high gyrobohm flux | Turbulence & Transport | GA | No | No | No | |||
182 | Systematic test of paleoclassical transport | Turbulence & Transport | GA | No | No | No | |||
728 | 3D Fields Effects on Critical Gradient and Turbulence | Turbulence & Transport | GA | No | No | No | |||
457 | Prompt torque and zonal flow damping | Turbulence & Transport | GA | No | No | No | |||
430 | Test of Turbulence Spreading Using Turbulence Propagation | Turbulence & Transport | GA | No | No | No | |||
669 | Extrapolation of Low-Torque ITER Baseline Scenario With nu* and rho* | Turbulence & Transport | GA | No | No | No | |||
435 | Electron Critical Gradient in H-mode | Turbulence & Transport | GA | No | No | No | |||
17 | 3-D Fields and ECH Density Pumpout | Turbulence & Transport | GA | No | No | No | |||
18 | High Collisionless NBI Torque Drive for GAMs, aka the VH-mode path? | Turbulence & Transport | GA | No | No | No | |||
387 | 3-D Fields and ECH Density Pumpout | Turbulence & Transport | GA | No | No | No | |||
388 | High Collisionless NBI Torque Drive for GAMs, aka the VH-mode path? | Turbulence & Transport | GA | No | No | No | |||
325 | Document turbulence change with rotation in AI, and compare with theory | Turbulence & Transport | GA | No | No | No | |||
293 | Test of ETG zeff supression | Turbulence & Transport | GA | No | No | No | |||
294 | Simulated Alpha particle dillution | Turbulence & Transport | GA | No | No | No | |||
295 | preliminary simulated burn control | Turbulence & Transport | GA | No | No | No | |||
440 | Beam Density Affects on Carbon Density Profile | Turbulence & Transport | GA | No | 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 | |||
288 | Amplifying the Geodesic Acoustic Mode via Resonant Radial Field Amplification: New Methods | Turbulence & Transport | U of Wisconsin | No | No | No | |||
193 | Magnetic perturbation amplitude scan to investigate RMP-induced damping of Zonal Flows | Turbulence & Transport | U of Wisconsin | Yes | No | No | |||
86 | Safety Factor Scaling of Turbulence and Transport in Hybrid Scenario Plasmas | Turbulence & Transport | U of Wisconsin | No | No | No | |||
94 | Turbulence Structure and Amplitude Variation with ExB Shear in H-mode Plasmas | Turbulence & Transport | U of Wisconsin | No | No | No | |||
679 | Safety Factor Scaling of Turbulence and Transport in Hybrid Scenario Plasmas | Turbulence & Transport | U of Wisconsin | No | No | No | |||
682 | Amplifying the Geodesic Acoustic Mode via Resonant Radial Field Amplification: New Methods | Turbulence & Transport | U of Wisconsin | No | No | No | |||
683 | Confinement enhancement via impurity-seeding of H-mode plasmas | Turbulence & Transport | U of Wisconsin | No | No | No | |||
684 | Isotope Mass Scaling of Turbulence, Transport and Confinement in H-Mode | Turbulence & Transport | U of Wisconsin | No | No | No | |||
351 | Confinement enhancement via impurity-seeding of H-mode plasmas | Turbulence & Transport | U of Wisconsin | No | No | No | |||
594 | Aspect ratio scaling of turbulence and transport: DIII-D and NSTX-U comparison | Turbulence & Transport | U of Wisconsin | No | No | No | |||
623 | Trapped Electron Mode n_e / T_e Fluctuation Study | Turbulence & Transport | U of Colorado, Boulder | No | No | No | |||
624 | Trapped Electron Mode Study in Core | Turbulence & Transport | U of Colorado, Boulder | No | No | No | |||
26 | Investigate the role of RS on inward momentum transport | Turbulence & Transport | UCSD | No | No | No | |||
424 | Search for evidence of non-local transport across slow L-H transitions | Turbulence & Transport | Massachusetts Institute of Technology | Yes | No | No | |||
422 | Separation of thermal and particle transport in I-mode plasmas | Turbulence & Transport | Massachusetts Institute of Technology | No | No | No | |||
532 | Role of ECH Induced Mulitiscale Electron Thermal Transport in H-mode Plasmas | Turbulence & Transport | Massachusetts Institute of Technology | No | No | Yes | |||
533 | Between-shots gyrokinetic stability analysis | Turbulence & Transport | Massachusetts Institute of Technology | No | No | No | |||
37 | Identification of I-mode through simultaneous core and edge turbulence measurements | Turbulence & Transport | Massachusetts Institute of Technology | Yes | No | No | |||
420 | Identification of I-mode through simultaneous core and edge turbulence measurements | Turbulence & Transport | Massachusetts Institute of Technology | No | No | No | |||
362 | Investigation of GAMs during I-mode on D3D | Turbulence & Transport | Massachusetts Institute of Technology | No | Yes | No | |||
449 | Drift wave and NTM coupling | Turbulence & Transport | Los Alamos National Laboratory | Yes | No | No | |||
731 | Turbulent Ion Thermal Response to Electron Heat Flux and Te/Ti Variation | Turbulence & Transport | Sandia National Lab | No | No | No | |||
381 | Search for turbulence at ion-cyclotron frequencies | Turbulence & Transport | UCLA | No | No | No | |||
649 | Search for high freq magnetic fluctuations with CPS diagnostic | Turbulence & Transport | UCLA | No | No | No | |||
347 | Do differences in co/cnter GAM/ZF behavior affect deficit in gyrokinetic predicted Lmode transport? | Turbulence & Transport | UCLA | No | No | No | |||
671 | GAM eigenmode 2D structure | Turbulence & Transport | UCLA | No | No | No | |||
353 | Correlation length of electron temperature turbulence measurement and comparison with simulations | Turbulence & Transport | UCLA | No | No | No | |||
352 | Does increased turbulence in H-mode degrade agreement of GK transport/turbulence simulations? | Turbulence & Transport | UCLA | No | No | No | |||
668 | GAM eigenmode excitation mechanism and its impact on transport | Turbulence & Transport | UCLA | No | No | No | |||
356 | GAM eigenmode excitation mechanism | Turbulence & Transport | UCLA | No | No | No | |||
357 | GAM eigenmode 2D structure | Turbulence & Transport | UCLA | No | No | No | |||
349 | Density/current Scaling of Intrinsic Rotation and ITG/TEM Transition | Turbulence & Transport | UCLA | No | No | No | |||
651 | Achieve QH-mode plasmas with Te, Ti ~ 10 keV near mid-radius | Turbulence & Transport | UCLA | No | No | No | |||
639 | Electron thermal transport due to Compressional and Global AEs on DIII-D and projection to NSTX-U | Turbulence & Transport | UCLA | No | No | No | |||
564 | Simulated of Burn Control using In-Vessel Coils | Turbulence & Transport | PPPL | Yes | No | No | |||
393 | collisionality impact on momentum and particle transport | Turbulence & Transport | The college of William and Mary | No | No | No | |||
394 | Role of density and impurities on particle and momentum transport | Turbulence & Transport | The college of William and Mary | No | No | No | |||
76 | Connection between particle and momentum transport | Turbulence & Transport | The college of William and Mary | Yes | Yes | Yes | |||
417 | Comparison of H-Mode Transport with Co- and Ctr-NBI | Turbulence & Transport | ITER Organization | No | No | No | |||
502 | Energy Transport During Electron-Dominated Heating of ITER Baseline Scenario H-Mode Discharges | Turbulence & Transport | PPPL | No | No | No | |||
72 | Energy Transport During Electron-Dominated Heating of ITER-Relevant H-Mode Discharges | Turbulence & Transport | PPPL | Yes | No | No | |||
106 | Magnetic turbulence measurements in high beta H-mode discharges | Turbulence & Transport | PPPL | Yes | No | No | |||
779 | Measurement of the Heat Flux(Grad T) Function | Turbulence & Transport | U of Texas, Austin | No | No | No |