DIII-D RESEARCH OPPORTUNITIES FORUM FOR THE 2013 EXPERIMENTAL CAMPAIGN
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ID | Title | Research Area | Name | Affiliation |
Time Req'ed |
ITPA Joint Exp |
ITER IO Urgent Research Task |
274 details | Investigation of Momentum transport with Modulated ECH and ECH resonance layer sweeping | Plasma Rotation | National Fusion Research Institute | Yes | Yes | Yes | |
275 details | Investigation of Momentum transport with Modulated ECH and ECH resonance layer sweeping | Plasma Rotation | National Fusion Research Institute | Yes | Yes | Yes | |
276 details | Investigation of Momentum transport with power ratio P_ECH/P_NBI and torque ratio scan | Plasma Rotation | National Institute for Fusion Science, Toki, Japan | Yes | Yes | Yes | |
58 details | Progressing Towards a Staged Approach to Disruption Mitigation | Disruption Mitigation | GA | Yes | No | Yes | |
271 details | Investigation of Momentum transport with Modulated ECH and ECH resonance layer sweeping | Plasma Rotation | National Fusion Research Institute (NFRI), Korea | Yes | Yes | Yes | |
282 details | Investigation of Momentum transport with power ratio PECH/PNBI and torque ratio Ï?NBI/ PECH scan | Plasma Rotation | National Institute for Fusion Science, Toki, Japan | Yes | Yes | Yes | |
341 details | Investigation of Momentum Transport with Power ratio PECH/PNBI and torque ratio Ï?NBI/PECH scan | Plasma Rotation | National Institute for Fusion Science, Toki, Japan | Yes | Yes | Yes | |
342 details | Investigation of Core Poloidal Rotation Anomaly Change at ITG -> TEM transition | Plasma Rotation | National Fusion Research Institute (NFRI) | No | Yes | Yes | |
358 details | Investigation of Momentum transport with Modulated ECH and ECH resonance layer scan | Plasma Rotation | National Fusion Research Institute | Yes | Yes | Yes | |
296 details | Determine dependence of RWM marginal stability on rotation and energetic particles | Stability & Disruption Avoidance | Columbia U | Yes | Yes | Yes | |
338 details | Local correction of the TBM error field | Stability & Disruption Avoidance | Columbia U | No | No | Yes | |
132 details | Dissipation & Control of RE from ITER-like LSN targets | Disruption Mitigation | GA | No | No | Yes | |
3 details | The effect of LSN Shape on the q95 windows in RMP ELM Suppression | ELM Control | GA | No | No | Yes | |
250 details | Plateau Ecrit with MGI | Disruption Mitigation | GA | No | Yes | Yes | |
129 details | Optimization and Control of ITER-like MGI | Disruption Mitigation | GA | Yes | Yes | Yes | |
133 details | Fast Runaway Shutdowns by MGI | Disruption Mitigation | GA | Yes | Yes | Yes | |
309 details | Full 3D Rotation optimization of H mode | Stability & Disruption Avoidance | GA | No | Yes | Yes | |
220 details | Comparison of n=2 RMP field effects on ELMs and pedestal properties in KSTAR and DIII-D | ELM Control | GA | No | Yes | Yes | |
196 details | Narrow heat flux widths and divertor power dissipation | Divertor & SOL Physics | GA | Yes | Yes | Yes | |
171 details | Test of the argon pellet injector | Disruption Mitigation | ORNL | No | No | Yes | |
165 details | D2 + few % Ne shattered pellets for disruption mitigation | Disruption Mitigation | ORNL | No | No | Yes | |
166 details | Effect of q95 on SPI shutdown | Disruption Mitigation | ORNL | No | No | Yes | |
167 details | Control of radiation asymmetries by application of external field on SPI/MGI shutdown | Disruption Mitigation | ORNL | No | No | Yes | |
168 details | Influence of the delay time between multiple massive gas injections at different toroidal locations | Disruption Mitigation | ORNL | No | No | Yes | |
169 details | Runaway flattop mitigation by Neon shattered pellet injection | Disruption Mitigation | ORNL | No | No | Yes | |
161 details | n=3 offset and ELM suppression with RMP | ELM Control | GA | No | No | Yes | |
154 details | High frequency pellet ELM pacing | ELM Control | ORNL | No | Yes | Yes | |
155 details | Investigation of pellet induced ELM heat flux footprint variation with q95 | ELM Control | ORNL | No | No | Yes | |
157 details | Imaging of pellet induced ELM events from mulitple simultaneous views. | ELM Control | ORNL | No | No | Yes | |
181 details | Heat pulse propagation in a perturbed magnetic topology | ELM Control | GA | No | Yes | Yes | |
204 details | Suppression of Density Limit Disruptions with RMP Fields | Torkil Jensen Award | GA | No | No | Yes | |
184 details | Comparision DIII-D and AUG high collisionality ELM response to 3D magnetic perturbations | ELM Control | GA | No | Yes | Yes | |
205 details | SOL width in top-limited discharges | Divertor & SOL Physics | UCSD | No | No | Yes | |
314 details | Optimization of castellation for a new W-divertor of ITER: studies of shaped castellation in DIII-D | Plasma-material Interface | UCSD | No | Yes | Yes | |
135 details | Measurement of RE diffusion to center post | Disruption Mitigation | UCSD | No | No | Yes | |
136 details | Disruption main chamber heat loads | Disruption Mitigation | UCSD | No | Yes | Yes | |
139 details | TQ radiation distribution from R-2 MGI | Disruption Mitigation | UCSD | No | No | Yes | |
141 details | Studies of RE final loss | Disruption Mitigation | UCSD | No | No | Yes | |
137 details | 3D material migration during RMP ELM suppression | ELM Control | U of Wisconsin | Yes | Yes | Yes | |
78 details | 3D magnetics plasma response measurements of n=1 perturbations for RWM analysis & model validation | Stability & Disruption Avoidance | Department of Energy | Yes | No | Yes | |
79 details | 3D magnetics equilibrium measurements to applied n=3 perturbations | Stability & Disruption Avoidance | Department of Energy | Yes | No | Yes | |
80 details | Poloidal spectral measurements of n=3 RMP ELM suppression using the 3D magnetics upgrade | ELM Control | Department of Energy | Yes | No | Yes | |
102 details | TBM mock-up effects on confinement at high β | Stability & Disruption Avoidance | ITER Organization | Yes | No | Yes | |
113 details | Heat Load during slow current quench phase of disruptions/VDEs and its relation with poloidal halo c | Disruption Mitigation | ITER Organization | Yes | No | Yes | |
114 details | Toroidal peaking of radiation, response time for triggering TQ and mitigation efficiency during mass | Disruption Mitigation | ITER Organization | Yes | No | Yes | |
116 details | Influence of non-axisymmetric fields (TBMs / RMPs) on fast ion confinement and loss | Energetic Particles | ITER Organization | Yes | Yes | Yes | |
117 details | Conditions for nonlinear Alfvén Eigenmode evolution and impact on fast ion confinement and loss | Energetic Particles | ITER Organization | Yes | Yes | Yes | |
222 details | Investigation of optimum pellet injection geometry for pellet triggering minimum throughput/PFC flux | ELM Control | ITER Organization | Yes | No | Yes | |
223 details | Demonstration of integrated ELM-paced pellet fuelled H-mode plasma in ITER-relevant range. | ELM Control | ITER Organization | Yes | Yes | Yes | |
224 details | Determination of minimum confinement degradation for ELM suppression with I coils | ELM Control | ITER Organization | Yes | No | Yes | |
229 details | CQ de-confinement of REs using pulsed impurity injection | Disruption Mitigation | ITER Organization | Yes | No | Yes | |
226 details | Compatibility of ELM suppressed regimes by 3-D fields with pellet injection for plasma fuelling | ELM Control | ITER Organization | Yes | No | Yes | |
227 details | Mechanisms leading to termination of the runaway discharges and effects on PFC energy deposition | Disruption Mitigation | ITER Organization | Yes | No | Yes | |
87 details | farSOL expts at high n/nGW to establish if ITER farSOL will be high-recycling/detached | Divertor & SOL Physics | U of Toronto | Yes | No | Yes | |
88 details | inner column limiter expts to establish if ITER wall-limiter design should include �??funnel effect' | Divertor & SOL Physics | U of Toronto | Yes | No | Yes | |
89 details | Mo, W, Al, Be DiMES net/gross erosion experiments | Plasma-material Interface | U of Toronto | Yes | Yes | Yes | |
66 details | 13C-methane injection into USN re C migration to walls and ITER decision about PFC target material | Plasma-material Interface | U of Toronto | Yes | Yes | Yes | |
49 details | Turbulent transport in detached divertor | Divertor & SOL Physics | UCSD | No | No | Yes | |
25 details | Transport mechanisms induced by RMP | ELM Control | UCSD | No | No | Yes | |
263 details | Radiative divertor solutions in the ITER baseline scenario | Inductive Scenarios | ITER Organization | No | Yes | Yes | |
264 details | Radiative divertor solutions in the ITER baseline scenario | Divertor & SOL Physics | ITER Organization | No | Yes | Yes | |
76 details | Connection between particle and momentum transport | Turbulence & Transport | The college of William and Mary | Yes | Yes | Yes | |
343 details | Evaluating Physics of RMP Stationary Enhanced Confinement Regime Without ELMs for the 2013 JRT | ELM Control | LLNL | No | No | Yes | |
101 details | Investigation of n=1 RMP effects on ELMs with pitch-aligned configuration of I-coils | ELM Control | PPPL | Yes | Yes | Yes | |
131 details | Understanding runaway equilibrium to minimize damage hazard | Disruption Mitigation | Yes | Yes | Yes | ||
368 details | Investigation of extreme outer wall heating caused by the DIII-D TBM | Plasma-material Interface | LLNL | No | Yes | Yes | |
230 details | Assessment of the degree of detachment using NIR spectroscopy | Divertor & SOL Physics | LLNL | Yes | No | No | |
225 details | Study of atomic and molecular processes in deep detachment conditions | Divertor & SOL Physics | LLNL | Yes | No | No | |
228 details | High resolution study of collisionality and target structure in the transition to full detachment | Divertor & SOL Physics | LLNL | Yes | No | No | |
311 details | Transport with qmin>2 | Steady State Heating and Current Drive | LLNL | No | No | No | |
71 details | 4. ELM Characterization to Validate BOUT++ ELM Simulations | Pedestal Structure | LLNL | No | No | No | |
234 details | Study fishbone-like instability at the edge of QH-modes | Inductive Scenarios | Instituto Superior Tecnico, Lisboa, Portugal | No | No | No | |
291 details | 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 | |
367 details | JET/DIII-D similarity experiment on rotation in plasmas with low momentum input | Plasma Rotation | Instituto Superior Tecnico, Lisboa, Portugal | No | Yes | No | |
209 details | RMP ELM-Control for Snowflake Configurations | Torkil Jensen Award | LLNL | Yes | No | No | |
156 details | Controlling the timing and evolution of L-H and H-L with 3D fields | Plasma Control | PPPL | Yes | No | No | |
24 details | Plasma response to 3D magnetic perturbations in the unfavorable grad-B drift direction | ELM Control | PPPL | Yes | No | No | |
41 details | Investigation of the effects of the EHO toroidal mode number on the edge particle transport | Inductive Scenarios | PPPL | No | No | No | |
376 details | Role of q and magnetic shear of pedestal formation time and turbulent transport | Pedestal Structure | PPPL | No | No | No | |
212 details | Island seeding with saw teeth pacing: New method to control tearing modes | Stability & Disruption Avoidance | PPPL | Yes | No | No | |
213 details | Real-time Ray Tracing for PCS | Plasma Control | PPPL | Yes | No | No | |
214 details | Density (Greenwald) Limit and the Radiation Driven Islands | Torkil Jensen Award | PPPL | Yes | No | No | |
216 details | Campaign to study physics at the Greenwald limit | Steady State Heating and Current Drive | PPPL | Yes | No | No | |
217 details | PID (proportional integral derivative)control of Error Field | Stability & Disruption Avoidance | PPPL | Yes | No | No | |
218 details | Controlled Snowflake Divertor Study | Divertor & SOL Physics | PPPL | Yes | No | No | |
221 details | Gas Injection Feedback with Radiation Measurements | Divertor & SOL Physics | PPPL | Yes | No | No | |
208 details | qmin control | Steady State Heating and Current Drive | PPPL | Yes | No | No | |
198 details | Compare the power threshold for pre-emptive NTM suppression vs Catch and Subdue | Stability & Disruption Avoidance | PPPL | Yes | No | No | |
199 details | Reducing the tearing island detection time | Stability & Disruption Avoidance | PPPL | Yes | No | No | |
200 details | Multiple periods of NTM suppression | Stability & Disruption Avoidance | PPPL | Yes | No | No | |
201 details | NTM Control Upgrade: Capibility to deposit EC at multiple locations | Plasma Control | PPPL | Yes | No | No | |
202 details | Error Field Correction Improvement: Adding BetaN dependence | Stability & Disruption Avoidance | PPPL | Yes | No | No | |
130 details | Synergy between core-localized Alfven eigenmodes and edge localized TBM fields on fast ion losses. | Energetic Particles | PPPL | No | Yes | No | |
125 details | Observation of non-linear interactions in fast-ion loss spectra | Energetic Particles | PPPL | No | No | No | |
192 details | Measurement of heat flux on the divertor using the embedded thermocouple array | Divertor & SOL Physics | U of Tennessee, Knoxville | No | No | No | |
149 details | 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 | |
126 details | Triggering ELMs at high frequency with PPPL Lithium granule injector | ELM Control | Retired from PPPL | Yes | No | No | |
21 details | Magnitude of cross-field drifts in the Private Flux Region, divertor asymmetries and detachment | Divertor & SOL Physics | Aalto U | No | No | No | |
22 details | Assessment of main chamber carbon sources | Divertor & SOL Physics | Aalto U | No | No | No | |
231 details | Stabilization of NTMs with ECCD | Stability & Disruption Avoidance | QST | No | Yes | No | |
211 details | Control of experimentally simulated burning state | Plasma Control | QST | Yes | No | No | |
128 details | 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 details | 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 | |
103 details | Probing and controlling the L->H and H->L transitions by small pellet injection | L-H Transition | Korea Institute of Fusion Energy | Yes | No | No | |
40 details | MGI with applied n=1 RMP fields | Disruption Mitigation | Fiat Lux LLC | No | No | No | |
344 details | Evaluating Physics of QH-mode Stationary Enhanced Confinement Regime Without ELMs for the 2013 J | Inductive Scenarios | LLNL | No | No | No | |
345 details | Evaluating Physics of I-mode Stationary Enhanced Confinement Regime Without ELMs for the 2013 JR | ELM Control | LLNL | No | No | No | |
179 details | Snowflake in AT Plasma | Steady State Heating and Current Drive | LLNL | No | No | No | |
142 details | ELM heat transport in the snowflake divertor. | Divertor & SOL Physics | LLNL | Yes | No | No | |
148 details | Radiative divertor control development | Divertor & SOL Physics | LLNL | Yes | No | No | |
134 details | Pedestal stability and divertor transport studies with feedback-controlled snowflake configuration. | Divertor & SOL Physics | LLNL | Yes | No | No | |
51 details | Study of chirping Alfvén eigenmodes in DIII-D | Energetic Particles | PPPL | No | Yes | No | |
52 details | Control of TAE/RSAE modes via external perturbations | Energetic Particles | PPPL | No | No | No | |
106 details | Magnetic turbulence measurements in high beta H-mode discharges | Turbulence & Transport | PPPL | Yes | No | No | |
150 details | Sensitivity study of toroidally-asymmetric halo current to error field during VDE | Disruption Mitigation | PPPL | No | No | No | |
138 details | SSI target improvement by minimizing global low-n MHD activity in 1.5 Steady State Heating and Current Drive | PPPL | No | No | No | | |
122 details | Bid farewell to locked modes - NTM-locking avoidance by feedback synchronization assisted with ECCD | Stability & Disruption Avoidance | PPPL | Yes | No | No | |
123 details | Bid farewell to locked modes - NTM-locking avoidance by feedback synchronization assisted with ECCD | Stability & Disruption Avoidance | PPPL | No | No | No | |
163 details | Exploration of DEFC in the feedback stabilized plasma in low-q discharges | Stability & Disruption Avoidance | PPPL | Yes | No | No | |
174 details | Exploration of DEFC in the feedback stabilized plasma in low-q discharges | Stability & Disruption Avoidance | PPPL | No | No | No | |
175 details | 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 details | Beta collapse avoidance in SSI discharges by de-synchronizing toroidal harmonics by using feedback | Steady State Heating and Current Drive | PPPL | No | No | No | |
177 details | Possibility of â??Off-axis-Fishbone Mode and ELM Pacingâ?? due to Direct Energetic Particle Coupling | ELM Control | PPPL | Yes | No | No | |
320 details | RWM excitation in the SSI target by reducing triangularity" | Stability & Disruption Avoidance | PPPL | No | No | No | |
377 details | NTM locking disruption avoidance by the EM torque with toroidal-phase forward magnetic feed | Disruption Mitigation | PPPL | No | No | No | |
329 details | Discussion of plasma rotation transient process during OFM/ELM-driven RWM w/wo feedback usin | Stability & Disruption Avoidance | PPPL | No | No | No | |
72 details | Energy Transport During Electron-Dominated Heating of ITER-Relevant H-Mode Discharges | Turbulence & Transport | PPPL | Yes | No | No | |
61 details | Energy Transport During Electron-Dominated Heating of ITER-Relevant H-Mode Discharges | Inductive Scenarios | PPPL | Yes | No | No | |
310 details | Energy Transport During Electron-Dominated Heating of ITER-Relevant H-Mode Discharges | Steady State Heating and Current Drive | PPPL | No | No | No | |
77 details | Influence of rotation and rotation shear on ELM suppression | ELM Control | The college of William and Mary | Yes | No | No | |
26 details | Investigate the role of RS on inward momentum transport | Turbulence & Transport | UCSD | No | No | No | |
27 details | COupling between core and SOL parallel flow | Divertor & SOL Physics | UCSD | No | No | No | |
28 details | Role of profile evolution and energy transfer in L-H transition | L-H Transition | UCSD | No | No | No | |
70 details | DIMES test of misaligned CFC tile to establish size of misalignment needed to disrupt ITER | Plasma-material Interface | U of Toronto | Yes | No | No | |
262 details | Test Pedestal Structure Model Where Paleoclassical Transport Is Dominant | Pedestal Structure | U of Wisconsin | No | No | No | |
305 details | Scaling Of Pedestal Plasma Transport With RMP I-coil Current | ELM Control | U of Wisconsin | No | No | No | |
359 details | q95 scaling of the coupled turbulence/zonal flow during LH transition | L-H Transition | U of Wisconsin | No | No | No | |
360 details | density scaling and X-point position scan of LH transition power threshold | L-H Transition | U of Wisconsin | No | No | No | |
62 details | RMP assisted snowflake divertor | Divertor & SOL Physics | U of Wisconsin | Yes | No | No | |
260 details | ITER Baseline Scenario Demonstration | Inductive Scenarios | ITER Organization | No | Yes | No | |
261 details | Demonstration of stationary inductive solutions at low and moderate q95 | Inductive Scenarios | ITER Organization | No | No | No | |
289 details | Demonstrate access to beta_N=5 with min(q)>2 | Steady State Heating and Current Drive | ITER Organization | No | No | No | |
283 details | ITER Baseline Scenario Operation near the LH Threshold | Inductive Scenarios | ITER Organization | No | Yes | No | |
284 details | Access conditions for steady-state operation in ITER | Steady State Heating and Current Drive | ITER Organization | No | Yes | No | |
285 details | Access to advanced inductive operation in ITER | Inductive Scenarios | ITER Organization | No | Yes | No | |
286 details | Collisionality scaling of confinement in advanced inductive regimes | Inductive Scenarios | ITER Organization | No | Yes | No | |
287 details | High li steady-state scenario development | Steady State Heating and Current Drive | ITER Organization | No | No | No | |
232 details | Bifurcated helical core equilibrium - continued | Stability & Disruption Avoidance | U of Wisconsin | Yes | No | No | |
256 details | Fine scale stepwise q-scan: role of low-order rationales and resonance condition for ELM suppression | ELM Control | U of Wisconsin | No | No | No | |
257 details | Transport Investigation During Slow Current Ramp-Up and Ramp-Down [for ITER] | Inductive Scenarios | U of Wisconsin | No | Yes | No | |
288 details | Amplifying the Geodesic Acoustic Mode via Resonant Radial Field Amplification: New Methods | Turbulence & Transport | U of Wisconsin | No | No | No | |
193 details | Magnetic perturbation amplitude scan to investigate RMP-induced damping of Zonal Flows | Turbulence & Transport | U of Wisconsin | Yes | No | No | |
86 details | Safety Factor Scaling of Turbulence and Transport in Hybrid Scenario Plasmas | Turbulence & Transport | U of Wisconsin | No | No | No | |
94 details | Turbulence Structure and Amplitude Variation with ExB Shear in H-mode Plasmas | Turbulence & Transport | U of Wisconsin | No | No | No | |
351 details | Confinement enhancement via impurity-seeding of H-mode plasmas | Turbulence & Transport | U of Wisconsin | No | No | No | |
104 details | Comparision of small-ELM regimes in DIII-D and NSTX | ELM Control | U of Wisconsin | Yes | No | No | |
109 details | Electron Heat Transport in E-Dominated Heating of ITER-like H-Mode Discharges with Modulated ECH | Inductive Scenarios | U of Wisconsin | Yes | No | No | |
110 details | Electron Heat Transport in E-Dominated Heating of ITER-like H-Mode Discharges with Modulated ECH | Turbulence & Transport | U of Wisconsin | Yes | No | No | |
316 details | Model-based control of the current profile and βN for steady state scenarios | Plasma Control | Cadarache | No | No | No | |
47 details | Quantifying the TBM torque, both in magnitude and radial location | Plasma Rotation | VTT Technical Research Centre | No | No | No | |
48 details | Dependence of momentum transport and intrinsic torque on rho* and beta | Plasma Rotation | VTT Technical Research Centre | No | Yes | No | |
73 details | Test optimized TBM error field correction at higher values of beta | Stability & Disruption Avoidance | CRPP-EPFL | Yes | No | No | |
74 details | Optimize TBM error field correction against field penetration in low NBI torque H-modes | Stability & Disruption Avoidance | CRPP-EPFL | Yes | No | No | |
75 details | Evaluate the potential of correcting more than one mode component of the TBM error field | Stability & Disruption Avoidance | CRPP-EPFL | Yes | No | No | |
91 details | Complete the Development of PCS n=2 Error Field Control Algorithm | Stability & Disruption Avoidance | Department of Energy | Yes | No | No | |
92 details | H-mode Optimization of n=1&2 Error Field Control Currents | Stability & Disruption Avoidance | Department of Energy | Yes | No | No | |
93 details | Active Control of the EHO in Quiescent H-modes | Plasma Control | Department of Energy | Yes | No | No | |
95 details | Experimental Validation of a Revised PCS Error Field Category | Plasma Control | Department of Energy | No | No | No | |
96 details | Effect of Error Field Control Currents on Strike Point Splitting | Stability & Disruption Avoidance | Department of Energy | No | No | No | |
290 details | Effect of n=2 Poloidal Spectrum on NTV Torque | Plasma Rotation | Department of Energy | No | No | No | |
366 details | Up/down Asymmetric EFC | Stability & Disruption Avoidance | Department of Energy | No | No | No | |
143 details | RMP ELM control at low torque | ELM Control | UCSD | Yes | No | No | |
144 details | Validation of kink response models with rotating n = 1 and n = 2 and phase flip n = 3 RMPs | ELM Control | UCSD | Yes | No | No | |
145 details | Explore RMP ELM suppression mechanism at moderate collisionality | ELM Control | UCSD | No | No | No | |
146 details | ELM suppression with Saturated walls | ELM Control | UCSD | Yes | No | No | |
147 details | Natural and Pellet-induced ELM behavior at low rotation/torque | ELM Control | UCSD | Yes | No | No | |
206 details | Studies of arcing on divertor PFC surfaces | Plasma-material Interface | UCSD | No | No | No | |
207 details | Dust generation from deposited layers and leading edges | Plasma-material Interface | UCSD | No | No | No | |
215 details | Control of tungsten PFC erosion by local gas injection | Plasma-material Interface | UCSD | No | No | No | |
219 details | Establishing an experimental basis for plasma effects on magnetic islands | ELM Control | GA | No | No | No | |
255 details | Super H-Mode | Torkil Jensen Award | ORNL | Yes | No | No | |
372 details | Pedestal optimization via impurity injection | Pedestal Structure | ORNL | No | No | No | |
373 details | Pedestal optimization in VH mode | Pedestal Structure | ORNL | No | No | No | |
374 details | Pedestal optimization with RMP ELM Control | Pedestal Structure | ORNL | No | No | No | |
375 details | QH-mode pedestal optimization | Inductive Scenarios | ORNL | No | No | No | |
332 details | Demonstration of noninductive Q=5 scenario in ITER shape using off-axis NBI | Steady State Heating and Current Drive | ORNL | No | No | No | |
333 details | Far off-axis NBCD | Steady State Heating and Current Drive | ORNL | No | No | No | |
334 details | Measurement of neoclassical response of off-axis beam ions | Steady State Heating and Current Drive | ORNL | No | No | No | |
335 details | Off-axis NBCD measurement in steady state scenario | Steady State Heating and Current Drive | ORNL | No | No | No | |
159 details | Collisionality dependence of pedestal height with RMP | Pedestal Structure | GA | Yes | No | No | |
317 details | Study on sawteeth in the neutral beam (NB) heated plasmas | Stability & Disruption Avoidance | Korea National Fusion Research Center | No | No | No | |
369 details | First-principles-driven Model-based Current-profile Control in H-mode Discharges | Plasma Control | Lehigh U | No | No | No | |
112 details | 2D imaging of small ELMs | ELM Control | Los Alamos National Laboratory | Yes | No | No | |
237 details | Critical electric field for runaway electron growth and decay under quiescent conditions | Disruption Mitigation | Massachusetts Institute of Technology | Yes | Yes | No | |
83 details | Establishing stationary I-mode with high performance | ELM Control | Massachusetts Institute of Technology | Yes | Yes | No | |
111 details | Dependence of I-mode on current direction and heating mix | ELM Control | Massachusetts Institute of Technology | Yes | Yes | No | |
362 details | Investigation of GAMs during I-mode on D3D | Turbulence & Transport | Massachusetts Institute of Technology | No | Yes | No | |
37 details | Identification of I-mode through simultaneous core and edge turbulence measurements | Turbulence & Transport | Massachusetts Institute of Technology | Yes | No | No | |
84 details | Influence of resonant/non-resonant magnetic perturbation on particle confinement with n=2 | ELM Control | Max-Planck Institute for Plasma Physics | Yes | Yes | No | |
121 details | Testing Emerging Two-Fluid Model for RMP Plasma Response in Straightforward IWL Plasmas | ELM Control | ORNL | Yes | No | No | |
124 details | Electron Energy Transport during q0 control using modulated EC power | Inductive Scenarios | ORNL | No | No | No | |
153 details | Controlling VH-mode with RMPs and comparison to NSTX EPH-mode | ELM Control | ORNL | Yes | No | No | |
55 details | RMP Elm Suppression in DN Plasmas | ELM Control | ORNL | No | No | No | |
56 details | Sawtooth Control | Plasma Control | ORNL | No | No | No | |
57 details | Develop a high performance L-mode plasma. | General Physics | ORNL | Yes | No | No | |
301 details | Access to the small ELM regime with a shape control | ELM Control | ORNL | Yes | No | No | |
107 details | Error field detection by application of a "spiraling" error field | Stability & Disruption Avoidance | ORNL | Yes | No | No | |
108 details | Disruption avoidance by forced magnetic spin-up of NTMs | Stability & Disruption Avoidance | ORNL | Yes | No | No | |
140 details | q0 control with Counter-ECCD in ITER Baseline Discharges | Inductive Scenarios | Retired | No | No | No | |
151 details | ITER SS Demo Discharge Documentations | Steady State Heating and Current Drive | Retired | No | No | No | |
235 details | High resolution Te pedestal measurements in RMP ELM suppression experiments | ELM Control | Sandia National Lab | No | No | No | |
127 details | Characterization of Intense Bursts of Millimeter Wave Emission in QH-mode Plasma | Inductive Scenarios | UC, Davis | Yes | No | No | |
38 details | Calibrated passive FIDA spectrum | Energetic Particles | UC, Irvine | No | No | No | |
39 details | Measure and understand energetic particle profiles in steady-state plasmas | Steady State Heating and Current Drive | UC, Irvine | No | No | No | |
339 details | Combined effect of TBM and NTM fields on fast-ion confinement | Stability & Disruption Avoidance | UC, Irvine | No | Yes | No | |
340 details | Combined effect of TBM and Sawtooth fields on fast-ion confinement | Stability & Disruption Avoidance | UC, Irvine | No | Yes | No | |
381 details | Search for turbulence at ion-cyclotron frequencies | Turbulence & Transport | UCLA | No | No | No | |
382 details | Transport and turbulence characterization experiment | Steady State Heating and Current Drive | UCLA | No | No | No | |
347 details | Do differences in co/cnter GAM/ZF behavior affect deficit in gyrokinetic predicted Lmode transport? | Turbulence & Transport | UCLA | No | No | No | |
348 details | Can we obtain ELM suppression without substantial loss of density? | ELM Control | UCLA | No | No | No | |
352 details | Does increased turbulence in H-mode degrade agreement of GK transport/turbulence simulations? | Turbulence & Transport | UCLA | No | No | No | |
353 details | Correlation length of electron temperature turbulence measurement and comparison with simulations | Turbulence & Transport | UCLA | No | No | No | |
355 details | q dependence of L-H transition power threshold | L-H Transition | UCLA | No | No | No | |
356 details | GAM eigenmode excitation mechanism | Turbulence & Transport | UCLA | No | No | No | |
357 details | GAM eigenmode 2D structure | Turbulence & Transport | UCLA | No | No | No | |
349 details | Density/current Scaling of Intrinsic Rotation and ITG/TEM Transition | Turbulence & Transport | UCLA | No | No | No | |
350 details | Current/Density Scaling of Intrinsic Rotation and ITG/TEM Transition | Plasma Rotation | UCLA | No | No | No | |
346 details | Control of H-L back transition via applied RMP fields | L-H Transition | UCLA | No | No | No | |
292 details | Optimize electron pedestal pressure in low-torque ITER baseline plasmas | Inductive Scenarios | UCLA | No | No | No | |
236 details | Wavenumber dependence of turbulence suppression in the L-H transition | L-H Transition | UCLA | No | No | No | |
2 details | Hysteresis and Turbulence Spreading in the H-L Back Transition | L-H Transition | UCLA | No | No | No | |
20 details | L-H transition Trigger Physics/ Main Ion Momentum Balance | L-H Transition | UCLA | No | No | No | |
308 details | RMP (Resonant Magnetic Perturbation) code validation via UCLA 288 GHz polarimeter | ELM Control | UCLA | No | No | No | |
265 details | o Experiments using the centerpost Swing-probes | Divertor & SOL Physics | UCSD | No | No | No | |
197 details | Scaling of divertor detachment onset | Divertor & SOL Physics | GA | Yes | No | No | |
378 details | Study of the connection between I-mode and low density Type III ELMs and optimization of I-mode | ELM Control | GA | No | No | No | |
379 details | Pedestal optimization of ITER baseline scenario discharges. | Pedestal Structure | GA | No | No | No | |
380 details | ELM Suppression at Lower Collisionality with Non-Resonant n=3 I-coil | ELM Control | GA | No | No | No | |
81 details | Active Particle Exhaust of H-mode Plasmas in the Snowflake-minus Divertor Configuration | Divertor & SOL Physics | GA | No | No | No | |
50 details | Improved Heat Load Reduction Using Long Outer Divertor Leg Geometry During Puff and Pump Operation | Divertor & SOL Physics | GA | Yes | No | No | |
59 details | Effect of Changing the Grad-B Drift Direction on Snowflake Divertor Behavior, Including Detachment | Divertor & SOL Physics | GA | No | No | No | |
42 details | Compatibility of High Performance Plasmas With a Puff-and-Pump Radiating Divertor | Steady State Heating and Current Drive | GA | No | No | No | |
43 details | Density Control and Active Impurity Removal from Double-null H-mode Plasmas | Divertor & SOL Physics | GA | No | No | No | |
44 details | Can Nitrogen impurity Seeding Improve Radiating Divertor Performance? | Divertor & SOL Physics | GA | No | No | No | |
45 details | Differences in Impurity Accumulation Between Resonant and Non-resonant RMP Plasmas | ELM Control | GA | No | No | No | |
46 details | Does Added Baffling From Re-Configured Tiles on the Lower Divertor Shelf Facilitate Detachment? | Divertor & SOL Physics | GA | No | No | No | |
29 details | Modulation of Bootstrap Current | ELM Control | GA | No | No | No | |
30 details | New Optimal Plasma Shape for AT Scenario? | Steady State Heating and Current Drive | GA | No | No | No | |
31 details | Test of Turbulence Spreading Using Turbulence Propagation | Turbulence & Transport | GA | No | No | No | |
32 details | High Beta Hybrids and Pressure Profile Broadening | Steady State Heating and Current Drive | GA | No | No | No | |
33 details | High Beta, Steady State Hybrids | Steady State Heating and Current Drive | GA | No | No | No | |
34 details | Electron Critical Gradient and Heat Pinch | Turbulence & Transport | GA | No | No | No | |
35 details | Non-Diffusive Heat Fluxes in the Edge "Shortfall" Region | Turbulence & Transport | GA | No | No | No | |
36 details | Natural ELM Pacing in High-Beta, Steady-State Plasmas | Steady State Heating and Current Drive | GA | No | No | No | |
313 details | Hybrids with co-NBI QH-mode edge | Inductive Scenarios | GA | No | No | No | |
302 details | RMP ELM Suppression at the NTV Offset Rotation | ELM Control | GA | No | No | No | |
303 details | Effect on lithium wall conditioning for Co-QH-mode and edge pedestal characteristics | Inductive Scenarios | GA | No | No | No | |
304 details | Birth of ITER: the world's largest resistor | General Physics | GA | No | No | No | |
300 details | Effect of triangularity in ITER shape and improved shaping | Inductive Scenarios | GA | No | No | No | |
297 details | ITER baseline scenario with low NBI torque | Inductive Scenarios | GA | No | No | No | |
298 details | Soft landing with 2/1 TM in the ITER shape | Stability & Disruption Avoidance | GA | No | No | No | |
363 details | TBM mockup simulating ITER GDC with ferritic materials | General Physics | GA | No | No | No | |
365 details | Lithium dropper commissioning and ELM modification | General Physics | GA | No | No | No | |
312 details | Limits to pedestal radiation high beta discharges | Steady State Heating and Current Drive | GA | No | No | No | |
17 details | 3-D Fields and ECH Density Pumpout | Turbulence & Transport | GA | No | No | No | |
18 details | High Collisionless NBI Torque Drive for GAMs, aka the VH-mode path? | Turbulence & Transport | GA | No | No | No | |
19 details | Effect of n=1 applied and error fields on n=3 RMP ELM suppression | ELM Control | GA | No | No | No | |
210 details | The Dependence of Poloidal Rotation on Turbulence | Plasma Rotation | GA | No | No | No | |
4 details | Turbulence and Intrinsic Rotation | Plasma Rotation | GA | No | No | No | |
5 details | Measure Intrinsic Rotation Size scaling in DIII-D alone -II | Plasma Rotation | GA | No | No | No | |
23 details | RMP ELM Suppression at q95 above 4 | ELM Control | GA | No | No | No | |
158 details | 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 details | Dependence of confinement and stability on toroidal rotation in high li discharges | Steady State Heating and Current Drive | GA | No | No | No | |
164 details | 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 details | 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 details | Confinement and fast ion diffusion in high betaN, steady-state scenario discharges | Steady State Heating and Current Drive | GA | No | No | No | |
162 details | 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 details | Beta limit and bootstrap current fraction in ITER steady-state scenario discharges | Steady State Heating and Current Drive | GA | No | No | No | |
180 details | Establish the incremental confinement of EC power in high betaN steady-state scenario discharges | Steady State Heating and Current Drive | GA | No | No | No | |
242 details | q95 < 2 Tokamak Operation Via Dynamic Error Field Correction | Stability & Disruption Avoidance | GA | No | No | No | |
243 details | 256: SOL width and divertor peak heat flux in QH-mode plasmas with/without n=3 fields | Inductive Scenarios | GA | No | No | No | |
244 details | Study NRMF driven torque in ECH-only heated plasma (ELMing H-modes) | Plasma Rotation | GA | No | No | No | |
245 details | Investigate the physics of NTM suppression by large externally applied helical fields | Torkil Jensen Award | GA | No | No | No | |
246 details | Develop low-torque, high normalized fusion performance QH-mode for ITER baseline scenario | Inductive Scenarios | GA | No | No | No | |
247 details | Develop low-torque, high normalized fusion performance QH-mode for FNSF-AT scenario | Inductive Scenarios | GA | No | No | No | |
248 details | Investigate elongation limit in low li discharges with/without applied 3D magnetic fields | Torkil Jensen Award | GA | No | No | No | |
249 details | Steady-state high beta with NCS and qmin>2 | Steady State Heating and Current Drive | GA | No | No | No | |
370 details | Particle pinch in pedestal | Pedestal Structure | GA | No | No | No | |
371 details | Effect of icoil current on energy confinement in RMP ELM-suppressed discharges | ELM Control | GA | No | No | No | |
254 details | Neon SPI injection into early CQ to stunt RE formation | Disruption Mitigation | GA | No | No | No | |
252 details | Implement finite-state Off Normal Fault Response system | Plasma Control | GA | No | No | No | |
6 details | Prompt torque and zonal flow damping | Plasma Rotation | GA | No | No | No | |
7 details | Investigate angular momentum diffusion and pinch using off-axis torque | Plasma Rotation | GA | No | No | No | |
8 details | Compare Mach probe and CER measurements of intrinsic rotation profile of main ions in helium plasma | Plasma Rotation | GA | No | No | No | |
9 details | Test of Neoclassical Toroidal Viscosity theory using modulated I-coil currents | Plasma Rotation | GA | No | No | No | |
10 details | Maintain low-rotation QH-mode with ECH only | Inductive Scenarios | GA | No | No | No | |
11 details | Investigate in-out density asymmetry at large toroidal rotation | Plasma Rotation | GA | No | No | No | |
12 details | Diagnostic spatial cross calibration using edge sweeps in QH-mode | Pedestal Structure | GA | No | No | No | |
13 details | Compare edge particle transport in ELMing H-mode and QH-mode with and without NRMF | Inductive Scenarios | GA | No | No | No | |
14 details | Control of toroidal mode number of EHO | Inductive Scenarios | GA | No | No | No | |
15 details | Edge rotation shear threshold for QH-mode access | Inductive Scenarios | GA | No | No | No | |
16 details | Further development of QH-mode with strong co-Ip NBI torque | Inductive Scenarios | GA | No | No | No | |
53 details | QH-mode with low torque start-up | Inductive Scenarios | GA | No | No | No | |
115 details | QH-mode at low co-Ip torque using n=2 NRMF | Inductive Scenarios | GA | No | No | No | |
120 details | Optimizing non-resonant, nonaxisymmetric fields in QH-mode | Inductive Scenarios | GA | No | No | No | |
364 details | Absolute plasma response null measurement by multiple betaN steps | Stability & Disruption Avoidance | Columbia U | No | No | No | |
354 details | Control of Major Disruptions in DIII-D | Stability & Disruption Avoidance | Columbia U | No | No | No | |
203 details | Dynamic plasma-wall equilibrium in ELMy H-mode | Divertor & SOL Physics | CompX | Yes | No | No | |
105 details | Optimization and exploration of the q95<2 scenario in DIII-D | Stability & Disruption Avoidance | Consorzio RFX | Yes | No | No | |
361 details | Dither injection for closed-loop system identification of vacuum and plasma response | Stability & Disruption Avoidance | Consultant | No | No | No | |
185 details | Measure Plasma Response to RMPs | ELM Control | GA | Yes | No | No | |
251 details | New Study of Alfven Eigenmodes Induced Fast Ion Transport/Loss | Energetic Particles | GA | No | No | No | |
253 details | Study QH-mode with advanced fast ion diagnostics and codes | Inductive Scenarios | GA | No | No | No | |
1 details | C vs I Coil NTV | Plasma Rotation | GA | No | No | No | |
152 details | Transport shortfall at high gyrobohm flux | Turbulence & Transport | GA | No | No | No | |
182 details | Systematic test of paleoclassical transport | Turbulence & Transport | GA | No | No | No | |
330 details | QH-mode with TBM | Inductive Scenarios | GA | No | No | No | |
331 details | QH-mode with TBM (dup 330) | Stability & Disruption Avoidance | GA | No | No | No | |
170 details | Nature of Energy Released During H-L Back Transition | L-H Transition | GA | No | No | No | |
258 details | Main-ion and impurity rotation in helium plasmas | Plasma Rotation | GA | No | No | No | |
259 details | Helium Campaign (D beams) | General Physics | GA | No | No | No | |
293 details | Test of ETG zeff supression | Turbulence & Transport | GA | No | No | No | |
294 details | Simulated Alpha particle dillution | Turbulence & Transport | GA | No | No | No | |
295 details | preliminary simulated burn control | Turbulence & Transport | GA | No | No | No | |
241 details | C-13 and background carbon | Plasma-material Interface | GA | No | No | No | |
233 details | C erosion and D up-take at high surface temperature | Plasma-material Interface | GA | No | No | No | |
194 details | Correlation of confinement and fluctuations with electron heating in ITER Baseline Scenario | Inductive Scenarios | GA | No | No | No | |
195 details | Correlation of confinement and fluctuations with electron heating in ITER Baseline Scenario | Turbulence & Transport | GA | No | No | No | |
60 details | Effective NTM control in low torque plasmas | Stability & Disruption Avoidance | GA | No | No | No | |
321 details | Access to low torque QH-mode using high beta low torque AI target with NRMF | Inductive Scenarios | GA | No | No | No | |
322 details | ELM pacing in low torque, electron heated ITER baseline | Inductive Scenarios | GA | No | No | No | |
323 details | Access to QH-mode with low NBI torque | Inductive Scenarios | GA | No | No | No | |
324 details | Document turbulence change with rotation in AI, and compare with theory | Inductive Scenarios | GA | No | No | No | |
325 details | Document turbulence change with rotation in AI, and compare with theory | Turbulence & Transport | GA | No | No | No | |
326 details | Understand mechanisms by which ECH influences NTM stablility | Stability & Disruption Avoidance | GA | No | No | No | |
327 details | rho* scaling of intrinsic torque between DIII-D and JET | Plasma Rotation | GA | No | Yes | No | |
328 details | Error field correction at low rotation | Stability & Disruption Avoidance | GA | No | No | No | |
82 details | IR Imaging of I-coil Induced Fast Ion Losses | Energetic Particles | GA | No | Yes | No | |
315 details | Current profile control model requirements | Plasma Control | GA | No | No | No | |
336 details | Routine current profile control in operation | Steady State Heating and Current Drive | GA | No | No | No | |
337 details | Routine current profile control in operation | Inductive Scenarios | GA | No | No | No | |
318 details | Current profile control for stable ITER baseline scenario plasmas | Inductive Scenarios | Columbia U | No | No | No | |
319 details | Impact of fast-ions on the RWM stability boundary | General Physics | Columbia U | No | No | No | |
118 details | Dominant electron heated ITER baseline scenario studies | Inductive Scenarios | Columbia U | Yes | No | No | |
119 details | Impact of fast-ions on the RWM stability boundary | Stability & Disruption Avoidance | Columbia U | Yes | Yes | No | |
85 details | Current profile control for stable ITER baseline scenario plasmas | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |
97 details | Time-resolved measurement of plasma response spectrum | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |
98 details | Develop feedback-controlled MHD spectroscopy | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |
99 details | Understand and control resistive wall mode stability in high-qmin plasmas | Stability & Disruption Avoidance | Columbia U | Yes | Yes | No | |
100 details | Understand resistive wall mode control physics in low-q95 plasmas | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |
266 details | Understand resistive wall mode control physics in low-q95 plasmas | Inductive Scenarios | Columbia U | No | No | No | |
267 details | Understand and control resistive wall mode stability in high-qmin plasmas | Steady State Heating and Current Drive | Columbia U | No | No | No | |
238 details | Direct Measurement of NTV Torque | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |
239 details | Continuous Scan of NTV Torque Across Low Rotation Peak | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |
240 details | Optimization of Applied Error Field Spectrum for NTV | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |
186 details | Optimal Mixing of I & C coils for n=1 EFC | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |
187 details | H-mode 3-D field optimization with purely kink-resonant and non-resonant n=1 fields | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |
188 details | Extension of proxy error field experiments to H-mode plasmas | Stability & Disruption Avoidance | Columbia U | No | No | No | |
189 details | Measurement of optimal n=2 phasing for RMP & ELM suppression without q95 windows | ELM Control | Columbia U | No | No | No | |
190 details | Measurement of n=3 error field effects in RMP phase-flip experiments | ELM Control | Columbia U | No | No | No | |
191 details | Critical electric field for runaway electron growth and decay under quiescent conditions | Disruption Mitigation | Columbia U | Yes | Yes | No | |
183 details | Measurement of multiple mechanisms in the low-density limit via ellipticity in the compass scan | Stability & Disruption Avoidance | Columbia U | Yes | No | No | |
299 details | Aspect ratio scaling of turbulence and transport: DIII-D and NSTX-U comparison | Turbulence & Transport | Univ. Wisconsin (at PPPL) | No | No | No | |
306 details | Edge turbulence and blob generation | Divertor & SOL Physics | Univ. Wisconsin | No | No | No | |
307 details | Role of turbulent-driven and Ion pressure gradient-sustained ExB flows in Triggering H-mode | L-H Transition | UCSD | No | No | No | |
272 details | Dither injection for closed-loop system identification of vacuum and plasma response | Torkil Jensen Award | KTH | Yes | No | No | |
273 details | Sawtooth control via n=1 external magnetic perturbation | Torkil Jensen Award | Consorzio RFX and Padova U | Yes | No | No | |
268 details | nu* dimensionless scaling | Turbulence & Transport | CEA | No | Yes | No | |
270 details | L-mode Turbulence and L-H Transition Characterization in Snowflake Divertor Plasmas | Divertor & SOL Physics | LLNL | Yes | No | No | |
277 details | ECH effects on low or balanced torque discharges in DIII-D | Plasma Rotation | National Fusion Research Institute (NFRI), Korea | Yes | Yes | No | |
278 details | Possibility of â??Off-axis-Fishbone Mode and ELM Pacingâ?? due to Direct Energetic Particle Coupling | ELM Control | JAEA | No | No | No | |
279 details | ECH effects on low or balanced torque discharges in DIII-D | Plasma Rotation | National Fusion Research Institute (NFRI), Korea | Yes | Yes | No | |
280 details | : 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 details | ECH effects on low or balanced torque discharges in DIII-D | Plasma Rotation | National Fusion Research Institute (NFRI), Korea | Yes | Yes | No |