1 DIII-D Edge physics overview A.Leonard for the Plasma Boundary Interface Group Presented at the PFC Meeting UCLA, August 4-6, 2010

2 Plasma Boundary Interface 2010 Experimental Topics PBI was allocated 6.5 days of experimental time Complete Joint Research Target on Boundary heat flux –Complete parameter scan of divertor heat flux width –C-Mod comparison –Measure fluctuation driven radial heat transport in boundary Fuel Retention and Clean-up –Determine fraction of injected fuel tightly bound in vessel wall –Utilize bake in oxygen to remove fuel co-deposited with eroded carbon DiMES –Understanding divertor carbon chemical erosion ITER first wall design issues –Heat flux profile onto startup/rampdown limiters –ELM heat flux into secondary divertor

3 Boundary Heat Flux Joint Research Task Completed DIII-D Scaling Studies Completed divertor heat flux width scaling –Power; No dependence –Collisionality; No dependence –Toroidal Field; Weak, or no dependence –Plasma Current; Inverse Dependence DIII-D Heat flux scaling  q (cm, midplane) ~ 0.7/Ip (MA) –implies for a diffusive model Size scaling to be tested across devices –A diffusive model of transport would imply q ∝ R 1/2 Further Analysis –Power balance, radiated power –Statistical analysis Heat Flux Width

4 DIII-D Divertor Heat Flux Compared with Alcator C-Mod A comparison between DIII-D and Alcator C-Mod has been completed –Comparison at same shape and q 95 –Density scan matched collisionality –Power scan indicated no heat flux width dependence on power; lends confidence to the noisier data low power for matched edge conditions Initial C-Mod data has been acquired –Initial estimate of C-Mod width indicates a positive size scaling Additional analysis with C-Mod underway –Examine size scaling of divertor heat flux widths and upstream profiles to determine consistency with diffusive transport, or a constant gradient C-Mod Shape in DIII-D

5 Characteristics of Near SOL Fluctuations to Offer Insight into Heat Flux Transport Mechanisms Initial set of measurements from midplane Langmuir probe of fluctuation driven heat transport –Initial data set from midplane and X-point probe –Plasma current and density scan Analysis has only just begun –Examine correlation of turbulence region with divertor heat flux footprint –Dominance of convective transport could indicate interchange-like transport –Planning comparison with turbulence codes

6 Heat Flux Joint Research Task Summary A complete parameter scan taken –Initial analysis indicates I p dominant parameter affecting width –Detailed statistical analysis tasks remain Upstream profiles acquired –Thomson data unclear if adequate to discern trends –Apply other analysis techniques to Thomson analysis –Upstream probe data yet to be fully compared with divertor heat flux Size scaling analysis underway –Comparison with C-Mod awaits further C-Mod analysis –Good dataset from JET/DIII-D pedestal comparison also to be analyzed

7 Goal of Fuel Retention Studies: Determine How Much Fuel Tightly Retained and Clean It Up Dynamic particle balance indicates most fuel is retained during the plasma ramp-up phase –Successful comparison of ‘static’ to ‘dynamic’ particle balance –Little retention during H-mode phase A bake after operations removed much of the retained fuel –A day of continuous particle balance preceded and followed by a bake A successful Oxygen bake –Nothing destroyed(by oxygen) –Rapid restoration of high performance discharges –Removed expected fraction of carbon deposits and deuterium co-deposits

8 Typical Dynamic Balance has Phases of Retention Phase-I:Pre-fill & Breakdown –No net retention Phase-2: Ramp-up –Large wall uptake –Dominated by puffing Phase-3: early H-mode –ELM-free; n e build-up –Net wall release Phase-4: H-mode steady- state –No measurable retention Phase-I Phase-2 Phase-3 Phase-4 time [sec] Time (msec) Γ IN [Torr-L/s] Γ wall [Torr-L/s] ∫ Γ wall [Torr-L] Q pump [Torr-L/s] Wall uptake Wall inventory

9 Pumping Speed Compares Well with Cryopump Regeneration Set #1Set #2Set #3Set #4Set #5 Set #1Set #2 Set #3 Set #4 Set #5 5% 4% 2%0.5% Exhausted Particles [Torr-L] Comparison of Time-resolved vs Shot-integrated Exhausted Particles Careful calibration of dynamic balance diagnostics completed Multiple shots used for better accuracy in static balance Allows confidence in dynamic balance results

10 Complete Run-day Analysis Gives ~ 20% Gas Retention Static balance used capacitance manometer –Multiple shots to increase accuracy; Error ~ 1.5% Dynamic balance for whole shot (ramp-up & steady-state H-mode) 4 shots 1 shot Cumulative Exhaust vs Injected Particles for a Full Run-day

11 Vacuum Bake Before and After Single Run-day Used to Deplete and Recover Wall Inventory Goal is to determine fraction of injected particles than can be easily removed Pre-operation vacuum bake to deplete recoverable wall inventory Post-operation vacuum bake after run day to recover loosely bound particles –Limited bake time (i.e., pressure did not turn over)

12 Vacuum Bake Before and After Single Run-day Returned Large Fraction of Retained Particles Particle balance summary –Total injected : 2400 [torr-L] –Exhausted: [torr-L] –Bake released: 1090 [torr-L] Post-bake retention/total injected – [torr-L]/2400 ~7-12% 7-12% Would more be released from higher/longer bake? –But co-dep removal starts ~700°C

13 Co-deposited D Could Account for Fuel Left After Vacuum Bake D left in machine – x10 22 D atoms ( Torr-L) Co-deposition retention estimate: Net C erosion yields: –Y phys ~1%, Y chem ~2% From experiment: ~ 4x10 23 D/s Assumed D/C ratios: –D/C Hard ~ ; D/C Soft ~ Ret HARD : x D atoms Ret SOFT : x10 22 D atoms = 165sec Deposition Pattern in Lower Divertor Region

14 Oxygen Bake Goals Demonstrate an oxygen bake on the DIII-D tokamak and recover high performance plasma operation (with only clean vents). –Assess “collateral damage” to tokamak systems –Operate tokamak systems – Pumps, ECH, ICH –Demonstrate 13 C removal on a few inserted tiles –Measure reaction products – RGA and FTIR Demonstrate removal of 13 C from several tiles with a second oxygen bake –DiMES will be only indication that 13 C deposited during repeat plasma shots –Oxygen Bake –Tiles removed for analysis at start of LTOA

15 Oxygen Bake Timeline

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17 The Heat Flux to the Secondary Divertor is a Significant Concern for ITER ITER will create secondary divertor when operating at high triangularity Primary concern is the ELM heat flux which can broader profile than the steady heat flux between ELMs Local recycling and SOL interaction also a concern due to re-deposition of eroded beryllium and co-deposition of tritium BX  B IRTV Secondary divertor Primary divertor Langmuir probes

18 Secondary divertor heat flux profile between ELMs is relatively broad but peaks at strike point The steady state heat flux in the secondary divertor (between ELMs) is: –peaked at the strike point with typical initial spatial decay –broader and more uneven than typical primary strike point profiles IRTV secondary divertor steady state heat flux EFIT OSP2 EFIT ISP2

19 Target plate heat flux profiles during an Elm show large peaks in the far SOL Large ELM peaks far outside strike- point –Not tied to physical features; tile gaps, or thin layers –Smaller ELMs have narrower profile Future analysis –ELM power balance; thermocouples, probes –Radial decay of ELM heat flux versus ELM size Δ t = 0.2 msec Δ t = 0.1 msec Δ t = 0.0 msec Δ t = 0.3 msec Δ t = 1.0 msec Tile gaps EFIT OSP2

20 Scaling of Limiter Heat Flux Consistent with ITER Assumptions Limiter heat flux examined to test ITER first wall design assumptions Measured widths are within range of assumed scaling, though parameter dependence not observed λ q measured (cm) λ q scaling (cm)