ITER-Research-Plan_final_ITR_FINAL-Cover_High-Res

ITR-18-003 ITER Research Plan within the Staged Approach (Level III – Provisional Version) ITER Organization ITR.support@iter.org 17 September 2018 ITER Research Plan within the Staged Approach (Level III – Provisional Version) ITR-18-003 ITER Research Plan LIII – Provisional Version Table of Contents ACRONYMS ACKNOWLEDGEMENTS 13 EXECUTIVE SUMMARY 14 INTRODUCTION 22 1.1 OBJECTIVES 22 1.2 METHODOLOGY 23 1.3 OVERALL STRUCTURE OF THE ITER RESEARCH PLAN PRESENT VERSION 25 1.3.1 ITER RESEARCH AND OPERATIONAL PHASES 25 1.3.2 ASSUMPTIONS ON THE PHASING OF ITER OPERATIONAL CAPABILITIES 27 1.3.3 KEY RESEARCH ISSUES 30 1.3.3.1 Key Research Issues during Operation 30 1.3.3.2 Key Research Issues during Construction 33 RESEARCH PROGRAM DURING OPERATIONS 35 2.1 OVERALL STRUCTURE OF THE EXPERIMENTAL PROGRAM DURING OPERATIONS 35 2.1.1 INTEGRATION OF THE RESEARCH PLAN INTO THE STAGED APPROACH 36 2.2 PLASMA-WALL INTERACTION (PWI) ISSUES FOR THE RESEARCH PLAN 37 2.2.1 CHARACTERISTICS OF HELIUM OPERATION 37 2.2.2 STEADY-STATE NEAR AND FAR SCRAPE-OFF LAYER (SOL) POWER WIDTHS (1/IP SCALING) 40 2.2.3 EDGE LOCALIZED MODE (ELM) POWER WIDTH SCALING 42 2.2.4 AMMONIA FORMATION DURING N2 SEEDING 43 2.2.5 DIFFERENCES IN MEDIUM-Z IMPURITY SEEDING (N2 VS NE) 43 2.2.6 TUNGSTEN-RELATED MATERIAL ISSUES 45 2.2.7 CASTELLATION GAP HEAT LOADS 46 2.2.8 RADIO-FREQUENCY-ASSISTED WALL CONDITIONING TECHNIQUES 47 2.2.9 DIVERTOR DETACHMENT CONTROL 48 2.2.10 PWI/PLASMA BOUNDARY CODE VALIDATION 49 2.3 PLASMA DISRUPTION MANAGEMENT 51 2.4 FIRST PLASMA 53 2.4.1 INTEGRATED COMMISSIONING 53 2.4.2 FIRST PLASMA 56 2.4.3 ENGINEERING OPERATION 56 2.5 PRE-FUSION POWER OPERATION PHASE (PFPO) 57 2.5.1 OBJECTIVES FOR THE PRE-FUSION POWER OPERATION PHASE 57 2.5.2 ASSUMPTIONS FOR PRE-FUSION POWER OPERATION 60 2.5.3 PLASMA SCENARIOS FOR HYDROGEN AND HELIUM OPERATION 62 2.5.3.1 First Plasma 64 2.5.3.2 First divertor plasma in PFPO-1 64 2.5.3.3 First q95 = plasma in PFPO-1 and PFPO-2 65 2.5.3.4 MA/1.8 T scenarios in PFPO-1 and PFPO-2 66 2.5.3.5 Progressive steps towards full current in PFPO-1 and PFPO-2 67 2.5.3.6 First full current plasma in PFPO-1 and PFPO-2 67 2.5.4 OPERATIONS PLAN FOR PFPO-1 68 ITR-18-003 2.5.4.1 PFPO-1 Objectives 68 2.5.4.2 Establishing routine operation with plasma to 3.5 MA divertor configuration 72 2.5.4.2.1 Commissioning of robust plasma initiation 72 2.5.4.2.2 Limiter operation up to 2MA 73 2.5.4.2.3 Limiter operation up to 3.5 MA 73 2.5.4.2.4 Divertor operation at 3.5 MA 74 2.5.4.2.5 Time required for obtaining routine divertor operation at 3.5 MA/2.65 T (hydrogen) 74 2.5.4.3 Validation of diagnostic data and demonstration of measurement consistency 75 2.5.4.4 Commission control, interlock and safety systems 77 2.5.4.4.1 Plasma Control (Conventional control) 77 2.5.4.4.2 Commissioning of the interlock system 79 2.5.4.4.3 Safety System commissioning 80 2.5.4.4.4 Control commissioning deliverables 80 2.5.4.5 Heating & Current Drive (H&CD) commissioning (ECRH, ICRF) in plasmas up to 7.5 MA/2.65 T 81 2.5.4.6 Disruption management program in PFPO-1 84 2.5.4.6.1 Disruption Mitigation System (DMS) commissioning/optimization 84 2.5.4.6.1.1 Confirmation of current quench heat load mitigation for 7.5 MA operation 85 2.5.4.6.1.2 Confirmation of thermal quench heat load mitigation in L-mode 85 2.5.4.6.1.3 Confirmation of EM load mitigation scheme for 7.5MA operation 86 2.5.4.6.1.4 Confirmation of the injection scheme with maximum margin to RE formation 86 2.5.4.6.1.5 Confirmation of the margin to RE generation in diverted configuration 86 2.5.4.6.2 Disruption Load Validation 87 2.5.4.6.2.1 Confirmation of EM load scaling models 87 2.5.4.6.2.2 Confirmation of melt thresholds for thermal loads during the current quench 87 2.5.4.6.2.3 Confirmation of melt thresholds for the divertor 87 2.5.4.6.2.4 Confirmation of melt thresholds for the first wall 87 2.5.4.6.3 Disruption Mitigation System (DMS) trigger generation 88 2.5.4.6.3.1 Disruption detection ready for high current operation 88 2.5.4.6.3.2 Thermal quench prediction sufficient for L-mode operation 89 2.5.4.6.3.3 Injection sequences ready for high current operation 89 2.5.4.6.3.4 Injection sequences ready for elevated thermal energies 89 2.5.4.7 Development of reliable operation at 7.5 MA/2.65 T 89 2.5.4.7.1 Establishing 7.5 MA/2.65 T divertor plasmas with heating 89 2.5.4.7.2 Studies of off-axis ECRH at 7.5 MA/2.65 T 90 2.5.4.8 Advanced control commissioning in PFPO-1 91 2.5.4.8.1 Plasma kinetic control 92 2.5.4.8.2 Magnetohydrodynamics (MHD) and Error Field control 94 2.5.4.8.3 Supervisory control 95 2.5.4.8.4 Advanced control commissioning deliverables for PFPO-1 96 2.5.4.9 Options for H-mode operation in PFPO-1 96 2.5.4.9.1 Summary of scenarios 96 2.5.4.9.2 Motivation for low field (1.8 T) operation in PFPO-1 98 2.5.4.9.3 Details of the experimental plan for H-mode operation in PFPO-1 99 2.5.4.9.3.1 First H-mode studies: initial H-mode operation in hydrogen plasma at MA/1.8 T (17 days) 99 2.5.4.9.3.2 First ELM control experiments MA/1.8 T (14 days) 100 2.5.4.9.3.3 H-mode in helium at 1.8 T and 5.0 MA (10 days) 103 2.5.4.9.3.4 Determination of the H-mode threshold in helium plasmas at ~ 2.65 T (3 days) 103 2.5.4.9.4 Deliverables for the H-mode operation campaign in PFPO-1 104 2.5.4.9.5 Assessment of diagnostic capabilities to perform H-mode research during PFPO-1 106 2.5.4.10 Edge physics and PWI studies in PFPO-1 107 ITR-18-003 2.5.4.10.1 Wall Conditioning and cleaning 107 2.5.4.10.1.1 Glow Discharge Cleaning 107 2.5.4.10.1.2 Ion Cyclotron Wall Conditioning/Electron Cyclotron Wall Conditioning 107 2.5.4.10.2 Fuel retention management 108 2.5.4.10.3 Gas balance in hydrogen 108 2.5.4.10.3.1 Ammonia formation during nitrogen-seeded discharges 109 2.5.4.10.3.2 Baking studies 109 2.5.4.10.3.3 Development of a ‘raised strike points’ scenario 109 2.5.4.10.4 Material migration studies 110 2.5.4.10.5 Limiter heat load characterization 110 2.5.4.10.6 Heat loads and detachment control during divertor operations 113 2.5.5 OPERATIONS PLAN FOR PFPO-2 115 2.5.5.1 PFPO-2 Objectives 115 2.5.5.2 Plasma restart in PFPO-2 (including influence of Test Blanket Modules) 118 2.5.5.2.1 Documenting the effect of the Test Blanket Modules (TBMs) during plasma restart 119 2.5.5.3 Heating & Current Drive (H&CD) commissioning (HNB, DNB, ICRF) 119 2.5.5.4 Diagnostics commissioning and validation 121 2.5.5.5 Disruption management program in PFPO-2 122 2.5.5.5.1 Disruption Mitigation System (DMS) commissioning/optimization 122 2.5.5.5.1.1 Confirmation of EM load mitigation at 15 MA 122 2.5.5.5.1.2 Confirmation of thermal quench heat load mitigation in H-mode 122 2.5.5.5.2 Disruption Load Validation 123 2.5.5.5.3 Disruption Mitigation System (DMS) trigger generation 123 2.5.5.5.3.1 Thermal quench prediction ready for FPO 123 2.5.5.5.3.2 Injection sequences ready for FPO 123 2.5.5.6 Advanced control commissioning in PFPO-2 124 2.5.5.6.1 Magnetic control 124 2.5.5.6.2 Plasma kinetic control 124 2.5.5.6.3 Magnetohydrodynamics (MHD) and error field control 126 2.5.5.6.4 Supervisory control 127 2.5.5.6.5 Advanced control commissioning deliverables 127 2.5.5.7 H-mode Studies in PFPO-2 128 2.5.5.7.1 Summary of scenarios 128 2.5.5.7.2 Motivation for H-mode scenarios in PFPO-2 131 2.5.5.7.3 Risk to the success of the H-mode studies in PFPO-2 132 2.5.5.7.4 Details of experimental plan and deliverables for H-mode scenarios in PFPO-2 134 2.5.5.7.4.1 H-mode operation to connect with PFPO-1, evaluate/mitigate TBM effects and to extend H-mode operation at 1.8T (40 days) 134 2.5.5.7.4.2 Expansion of H-mode operation towards 7.5 MA/2.65 T in hydrogen plasmas (10 days) 136 2.5.5.7.4.3 Expansion of H-mode operation towards 7.5 MA/2.65 T in helium plasmas (15 days) 138 2.5.5.7.4.4 Characterization of H-mode operation up to 7.5 MA/2.65 T including ELM control and resolution of scenario integration issues (40 days) 139 2.5.5.7.4.5 Demonstration of long-pulse H-mode operation (6 days) 142 2.5.5.7.4.6 Option for low ripple hydrogenic H-modes: H-mode in hydrogen at either 3.0 - 3.3 T and up to 8.5 or 9.5 MA respectively 144 2.5.5.7.5 Deliverables for the H-mode scenarios studies in PFPO-2 145 2.5.5.7.6 Assessment of diagnostic capabilities for performing H-mode research during PFPO-2 146 2.5.5.8 Scenarios for long-pulse operation 146 2.5.5.9 Demonstrate critical system performance (including heat loads) 147 2.5.5.9.1 Key elements of critical system performance 147 2.5.5.9.2 Critical system performance deliverables in PFPO-2 148 ITR-18-003 2.5.5.10 Initial studies of current drive efficiency, target q-profile formation and fast particle physics 149 2.5.5.10.1 Assessment of H&CD and diagnostic capabilities for performing current drive studies during PFPO-2 149 2.5.5.10.2 Risk to the initial studies of current drive efficiency, target q-profile formation and fast particle physics 150 2.5.5.10.3 Detailed experimental plan for the initial studies of current drive efficiency, target qprofile formation and fast particle physics (16 days) 151 2.5.5.10.4 Deliverables for the initial studies of current drive efficiency, target q-profile formation and fast particle physics 153 2.5.5.11 Plasma operation at full technical performance (15 MA/5.3 T) 153 2.5.5.11.1 Requirements 154 2.5.5.11.2 Risks to L-mode plasma operation at full technical performance (15 MA/5.3 T) 155 2.5.5.11.3 Detailed experimental plan for the expansion of L-mode plasma operation towards full technical performance (15 MA/5.3 T) (25 days) 155 2.5.5.11.4 Deliverables for the experimental plan for the expansion of L-mode plasma operation towards full technical performance (15 MA/5.3 T) 158 2.5.5.12 Edge physics and PWI studies in PFPO-2 159 2.5.5.12.1 Wall conditioning 159 2.5.5.12.2 Fuel retention and material migration 159 2.5.5.12.2.1 Deuterium trace experiment 159 2.5.5.12.2.2 Ammonia formation during nitrogen-seeded H-modes 161 2.5.5.12.2.3 Dust generation and characterization 162 2.5.5.12.2.4 Post-campaign analysis of Plasma-Facing Components 162 2.5.5.12.3 Heat loads during divertor operations 163 2.5.6 SUMMARY OF EXPERIMENTAL ACTIVITIES AND OPERATIONAL TIME IN THE PFPO PHASE 164 2.6 FUSION POWER OPERATION PHASE (FPO) 168 2.6.1 OBJECTIVES FOR THE FUSION POWER OPERATION PHASE 168 2.6.2 ASSUMPTIONS 172 2.6.3 OPERATION PLAN FOR DEUTERIUM PLASMA EXPERIMENTS 173 2.6.3.1 Plasma restart in FPO, including H&CD and Diagnostic commissioning 173 2.6.3.2 Disruption management program in FPO 174 2.6.3.3 Advanced control commissioning in FPO 175 2.6.3.3.1 Plasma kinetic control 175 2.6.3.3.2 MHD and error field control 176 2.6.3.3.3 Supervisory control 177 2.6.3.3.4 Deliverables for advanced control commissioning in FPO 177 2.6.3.4 Development of deuterium L-mode operation to 15 MA/5.3 T and first assessment of H-mode access at 2.65 T in D plasmas 177 2.6.3.4.1 Summary of scenarios and overall objectives 177 2.6.3.4.2 Requirements 178 2.6.3.4.3 Risks to the development of deuterium L-mode operation to 15 MA/5.3 T and first assessment of H-mode access at 2.65 T in D plasmas 178 2.6.3.4.4 Detailed experimental plan for the development of deuterium L-mode operation to 15 MA/5.3 T and first assessment of H-mode access at 2.65 T in D plasmas (32 days) 179 2.6.3.4.4.1 Detailed experimental plan for the development of deuterium L-mode operation to 15 MA/5.3 T (26 days) 179 2.6.3.4.4.2 L-H transition studies in preparation of H-mode operation in D plasmas (6 days) 179 2.6.3.4.5 Diagnostic adequacy for D plasma L-mode scenario studies in FPO 180 2.6.3.4.6 Deliverables for the development of deuterium L-mode operation to 15 MA/5.3 T and first assessment of H-mode access at 2.65 T in D 180 2.6.3.5 Development of deuterium H-mode plasmas towards full performance 181 ITR-18-003 2.6.3.5.1 Scenarios and overall objectives 181 2.6.3.5.2 Risk to the success of the D H-mode studies in FPO 182 2.6.3.5.3 Details of experimental plan for D plasma H-mode scenarios in FPO (40 days) 184 2.6.3.5.4 Diagnostic adequacy for D plasma H-mode scenario studies in FPO 187 2.6.3.5.5 Deliverables for D plasma H-mode scenario studies in FPO 187 2.6.3.5.6 Progress towards full machine parameters in D H-modes 188 2.6.3.6 Edge physics (including heat loads) and PWI studies in D plasmas 189 2.6.3.6.1 Wall conditioning 189 2.6.3.6.2 Fuel retention and material migration 190 2.6.3.6.3 Heat loads and detachment control 190 2.6.3.7 Trace Tritium H-mode experiments 192 2.6.3.7.1 Summary of scenarios and objectives 192 2.6.3.7.2 Risk to the success of the trace tritium H-mode experiments in FPO 192 2.6.3.7.3 Details of experimental plan for the trace tritium H-mode experiments in FPO (12 days) 193 2.6.3.7.4 Diagnostic adequacy for trace tritium H-mode scenario studies in FPO 194 2.6.3.7.5 Deliverables for the trace tritium H-mode experiments in FPO 194 2.6.3.8 Initial development of hybrid/ advanced scenarios 194 2.6.3.8.1 Summary of scenarios and overall objectives 194 2.6.3.8.2 Risk to the initial development for hybrid/ advanced scenarios 195 2.6.3.8.3 Detailed experimental plan for the initial development of hybrid/ advanced scenarios (2040 days) 196 2.6.3.8.4 Deliverables for the initial development of hybrid/ advanced scenarios 197 2.6.4 OPERATIONS PLAN FOR DEUTERIUM-TRITIUM (DT) PLASMA EXPERIMENTS TOWARDS Q = 10 198 2.6.4.1 Plasma scenarios for the experimental program towards Q = 10 operation 198 2.6.4.2 Optimization of DT plasma scenarios at 7.5 MA/2.65 T (66 days) 200 2.6.4.2.1 Experimental plans for the characterization of H-mode access (6 days) 200 2.6.4.2.2 Experimental plans for the exploration of DT H-mode at 7.5 MA/2.65 T (60 days) 201 2.6.4.2.3 Risks for exploration of DT H-mode at 7.5 MA/2.65 T 203 2.6.4.2.4 Deliverables from the exploration of DT H-mode at 7.5 MA/2.65 T 204 2.6.4.3 Optimization of fusion power in DT plasma scenarios towards 15 MA/5.3 T Q = 10 (~ 50 s) demonstration (180 days) 205 2.6.4.3.1 Risk to the optimization of fusion power in DT plasma scenarios towards 15 MA/5.3 T Q = 10 (~ 50 s) demonstration 211 2.6.4.3.2 Deliverables for the optimization of fusion power in DT plasma scenarios towards 15 MA/5.3 T, Q = 10 (~ 50 s) demonstration 212 2.6.4.4 Extension of the Q = 10 scenario towards long-pulse inductive operation (300 – 500 s) (100 days) 212 2.6.4.4.1 Risks and deliverable from the experimental phase to extend the Q = 10 scenario towards long-pulse inductive operation (300 – 500 s) 217 2.6.5 OPERATIONAL PLAN FOR HYBRID/NON-INDUCTIVE DT PLASMA EXPERIMENTS 217 2.6.5.1 Summary of scenarios and overall objectives 217 2.6.5.2 Risks to operational plan for hybrid/non-inductive DT plasma experiments 220 2.6.5.3 Experimental plan to develop DT scenarios for long-pulse hybrid and steady-state operation with high fusion power production 220 2.6.5.4 Deliverables from the operational plan for hybrid/non-inductive DT plasma experiments 225 2.6.6 BURNING PLASMA PHYSICS 226 2.6.6.1 Opportunities for burning plasma studies in DT plasmas 226 2.6.6.1.1 Fast particle physics and effects of non-axisymmetry 228 2.6.6.1.2 Self-heating and thermal stability 231 2.6.6.1.3 Macroscopic stability physics and control 232 2.6.6.1.4 Multi-scale transport physics 235 2.6.6.1.5 Physics of the plasma-boundary interface 235 ITR-18-003 2.6.7 SUMMARY OF EXPERIMENTAL ACTIVITIES AND OPERATIONAL TIME IN THE FPO PHASE 237 TECHNOLOGY RESEARCH PROGRAM 241 3.1 INTRODUCTION 241 3.2 TEST BLANKET MODULE (TBM) TESTING PROGRAM IN ITER 242 3.2.1 TEST BLANKET MODULE PROGRAM 242 3.2.1.1 Background and context for the TBM Program 242 3.2.1.2 TBM research program accompanying construction 245 3.2.1.2.1 R&D to be performed on TBMs and associated systems 245 3.2.1.2.2 Effect of TBM ferromagnetic structural material on plasma H-mode performance and fast ion losses 246 3.2.2 EXPERIMENTAL PROGRAM DURING OPERATION OF THE TBM TESTING PROGRAM IN ITER 248 3.2.2.1 Overall TBM testing strategy and objectives 249 3.2.2.2 Testing objectives for the Electro Magnetic Module (EM-TBM) 251 3.2.2.2.1 Role of the Electro Magnetic Module 251 3.2.2.2.2 General objectives 253 3.2.2.2.3 Specific objectives/ measurements for the Lithium-Lead TBM Systems 253 3.2.2.2.4 Specific objectives/ measurements for the Ceramic-Breeder TBM Systems 253 3.2.2.2.5 Special requirements for plasma operation scenarios in the PFPO-2 campaign 254 3.2.2.3 Testing objectives for the Thermal-Neutronic Module (TN-TBM) 254 3.2.2.3.1 Role of the Thermal-Neutronic Module 254 3.2.2.3.2 General objectives 254 3.2.2.3.3 Specific objectives/ measurements for the Lithium-Lead TBM Systems 255 3.2.2.3.4 Specific objectives/ measurements for the Ceramic-Breeder TBM Systems 255 3.2.2.3.5 Special requirements for plasma operation scenarios in the FPO-1 campaign 255 3.2.2.4 Testing objectives for the Neutronic-Tritium/Thermo-Mechanic Module (NT/TM-TBM) 255 3.2.2.4.1 Role of the Neutronic-Tritium/Thermo-Mechanic Module 255 3.2.2.4.2 General objectives 257 3.2.2.4.3 Specific objectives/ measurements for the Lithium-Lead TBM Systems 257 3.2.2.4.4 Specific objectives/ measurements for the Ceramic-Breeder TBM Systems 258 3.2.2.4.5 Special requirements for plasma operation scenarios in the FPO-2 campaign 258 3.2.2.5 Testing objectives for the INTegral TBM (INT-TBM) 258 3.2.2.5.1 Role of the INTegral Module 258 3.2.2.5.2 General objectives 259 3.2.2.5.3 Specific objectives/ measurements for the Lithium-Lead TBM Systems 259 3.2.2.5.4 Specific objectives/ measurements for the Ceramic-Breeder TBM Systems 259 3.2.2.5.5 Special requirements for plasma operation scenarios in the FPO-3 campaign 259 3.2.2.6 Overall achievements in the TBM Testing Program from PFPO-2 to the FPO-3 campaign – implications for later operations 260 3.2.3 SUMMARY AND CONCLUSIONS 262 UPGRADE OPTIONS AND REQUIRED R&D 263 4.1 HEATING AND CURRENT DRIVE SYSTEMS 265 4.1.1 BASELINE H-MODE ACCESS CAPABILITIES 265 4.1.2 STRATEGY TOWARDS H&CD UPGRADES 266 4.1.3 R&D NEEDS TO SUPPORT DECISIONS ON H&CD UPGRADES 266 4.2 FUELLING AND PUMPING UPGRADES 267 4.3 DIAGNOSTIC UPGRADES BEYOND THE 2016 BASELINE 269 4.4 UPGRADES OF PLASMA-FACING COMPONENTS AND MATERIALS 271 4.4.1 DIVERTOR 271 4.4.2 FIRST WALL 272 4.5 UPGRADES OF DISRUPTION MITIGATION SYSTEMS 273 ITR-18-003 4.6 UPGRADES TO PLASMA MAGNETIC CONTROL (VERSTICAL STABILIZATION, SHAPE, ERROR FIELDS, RESISTIVE WALL MODES) 274 4.6.1 PLASMA VERTICAL STABILIZATION 274 4.6.2 CONTROL OF PLASMA CURRENT POSITION AND SHAPE 275 4.6.3 CONTROL OF ERROR FIELDS 275 4.6.4 CONTROL OF RESISTIVE WALL MODES 276 4.7 UPGRADES REQUIRED FOR MAINTAINING LONG-PULSE OPERATION 276 4.8 UPGRADES FOR EXPLORATION OF DEMO PLASMA REGIMES AND FOR DEMO TECHNOLOGY DEMONSTRATION IN ITER 277 RESEARCH PROGRAM ACCOMPANYING CONSTRUCTION 282 5.1 H-MODE ISSUES 282 5.1.1 H-MODE RESEARCH RELATED TO PFPO-1 283 5.1.2 H-MODE RESEARCH RELATED TO PFPO-2 283 5.1.3 H-MODE RESEARCH RELATED TO DEUTERIUM AND TRACE T PLASMAS IN FPO 284 5.1.4 H-MODE RESEARCH RELATED TO HYBRID AND STEADY-STATE D PLASMAS IN FPO 284 5.1.5 H-MODE RESEARCH RELATED TO INDUCTIVE DT PLASMAS IN FPO 284 5.1.6 H-MODE RESEARCH RELATED TO HYBRID AND STEADY-STATE DT PLASMAS IN FPO 285 5.2 PLASMA-WALL INTERACTION ISSUES 285 5.3 MHD STABILITY ISSUES 288 5.3.1 DISRUPTION CHARACTERIZATION, PREDICTION AND MITIGATION 288 5.3.2 SAWTOOTH CONTROL 290 5.3.3 ELM CONTROL 291 5.3.4 NEOCLASSICAL TEARING MODE CONTROL 292 5.3.5 ERROR FIELD CONTROL 293 5.3.6 RESISTIVE WALL MODE CONTROL 294 5.4 SCENARIO DEVELOPMENT ISSUES 294 5.4.1 BREAKDOWN AND BURN-THROUGH 295 5.4.2 CURRENT RAMP-UP 296 5.4.3 CURRENT FLAT-TOP 296 5.4.4 PLASMA TERMINATION 297 5.4.5 IMPACT OF SCENARIO DEVELOPMENT ISSUES ON OPERATION 298 REFERENCES 300 APPENDIX A: USE OF DEUTERIUM SEEDING TO CHARACTERIZE FUEL RETENTION DURING PFPO-2 PHASE 312 APPENDIX B: L-H THRESHOLD AND TOROIDAL FIELD RIPPLE EFFECTS ON H-MODES 317 APPENDIX C: HEAT LOAD MANAGEMENT 326 APPENDIX D: REFERENCE PULSE 333 APPENDIX E: NON-INDUCTIVE SCENARIOS WITH/WITHOUT LHCD 334 APPENDIX F: PHYSICS ANALYSIS AND RISKS OF MA/1.8 T SCENARIOS 343 APPENDIX G: HEATING AND CURRENT DRIVE STAGING 356 APPENDIX H: DIAGNOSTIC STAGING 379 APPENDIX I: TRITIUM AVAILABILITY 401 APPENDIX J: RESEARCH PLAN RISK REGISTER 403 ITR-18-003 Acronyms ACCC AE Active Compensation and Correction Coils Alfvén Eigenmodes Tokamak operating between 1991 and 2016 at the Massachusetts Alcator C-Mod Institute of Technology ASDEX-Upgrade Tokamak developed at the Max-Planck-Institute for Plasma Physics BES Beam Emission Spectroscopy BLV Beam Line Vessel BSV Beam Source Vessel CC Correction Coils CCB Change Control Board CCWS Component Cooling Water System CEA Commissariat l’énergie atomique CI Coherence Imaging CIS Central Interlock System CODAC Control, Data Access and Communication CN-DA China Domestic Agency CQ Current Quench CS Central Solenoid CSs Cooling Systems CSS Central Safety System CTS Collective Thomson Scattering CX Charge-Exchange CXRS Charge Exchange Recombination Spectroscopy DA Domestic Agency DBC Disruption Budget Consumption DCLL Dual-Coolant Lithium-Lead DEFC Dynamic Error Field Correction DEMO Demonstration Fusion Reactor (next step after ITER) DIII-D Tokamak developed in the 1980s by General Atomics DIM Divertor Impurity Monitor DIP Density Interferometer Polarimeter DMS Disruption Mitigation System DNB Diagnostic Neutral Beam DT Deuterium-Tritium EAST Tokamak developed in Hefei, China EC European Commission EC Electron Cyclotron ECCD Electron Cyclotron Current Drive ECE Electron Cyclotron Emission (Diagnostic) ECH&CD Electron Cyclotron for Heating & Current Drive ECR Electron Cyclotron Resonance ECRH Electron Cyclotron Resonance Heating