ITER A/M/PMI Data Requirements and Management Strategy

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1 ITER A/M/PMI Data Requirements and Management Strategy Steven Lisgo, R. Barnsley, D. Campbell, A. Kukushkin, M. Hosokawa, R. A. Pitts, M. Shimada, J. Snipes, A. Winter ITER Organisation with contributions from C. Björkas (U. Helsinki/FZJ), D. Borodin (FZJ), R. Doerner (UCSD), F. Guzmán (U. Strathclyde/CEA), F. Imbeaux (CEA) The views and opinions expressed herein do not necessarily reflect those of the ITER Organization. S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 1

2 Outline Status of the ITER Project (6 slides) Overview of the ITER device (4 slides) Plasma environment and A/M/PMI processes (11 slides) Relevant ITER diagnostics (4 slides) ITER data management strategy (1 slide) Summary (1 slide) S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 2

3 Current status of the ITER platform S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 3

4 Completed site (2020) TOKAMAK BUILDING POWER SUPPLIES Steady 120 MW during operations, up to 620 MW for 30 s periods OFFICE BUILDING S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 4

5 ITER operation infographic TM Time H/He Non-active D/DT Radioactive Stored energy Commissioning of heat flux mitigation systems Required use of heat flux mitigation systems Impurity seeding, ELM control, disruption mitigation S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 5

tokamaks suggest that it may be easier (lower injected power) to enter H-mode in helium than in hydrogen during the non-nuclear phase if true,

6 Growing interest in helium: H-mode operation ELM: transient event observed at high confinement (H-mode) short but powerful bursts of particles and energy from the core to the boundary Type-I ELM s are associated with the highest observed energy confinement MAST TOKAMAK Data from tokamaks suggest that it may be easier (lower injected power) to enter H-mode in helium than in hydrogen during the non-nuclear phase if true, then helium operation may be critically important [from a slide by R. Pitts] S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 6

7 Outline Status of the ITER Project (6 slides) Overview of the ITER device (4 slides) Plasma environment and A/M/PMI processes (11 slides) Relevant ITER diagnostics (4 slides) ITER data management strategy (1 slide) Summary (1 slide) S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 7

8 The ITER tokamak R ~ 6 m h ~ 29 m S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 8

9 Overview of major systems S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 9

10 FULL-W START BASELINE Divertor strategies H/He D/DT H/He D/DT ~10 years S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 10

11 Plasma facing materials Why this mix of materials? ATOMIC NUMBER (ALLOWED MELTING CORE / SUBLIMATION CONCENTRATION Q=10) Be Fe (SS) C W (Cannot use an all C wall due to tritium retention) S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 11

12 Outline Status of the ITER Project (6 slides) Overview of the ITER device (4 slides) Plasma environment and A/M/PMI processes (11 slides) Relevant ITER diagnostics (4 slides) ITER data management strategy (1 slide) Summary (1 slide) S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 12

13 Predicted divertor plasma conditions (SOLPS code) Dissipation required low plasma temperature, high plasma density S. Lisgo / IAEA CRP A+M Data for Light Elements in Fusion Plasmas Page 13

14 Predicted conditions at the outer divertor target plate S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 14

Plasma flux to surfaces: plasma-wall contact Long-pulse, large size, and high density operation combine to give a significant increase in the ion fluence to the wall JET DIVERTOR ION FLUX COMPARISON

15 Plasma flux to surfaces: plasma-wall contact Long-pulse, large size, and high density operation combine to give a significant increase in the ion fluence to the wall JET DIVERTOR ION FLUX COMPARISON WITH JET ( , campaigns C1-C19) No. Pulses Time in Diverted Phase (hours) Outer Divertor Ion Fluence JET ~5x10 27 [1] ITER (Q=10) ~1.5x10 27 [2] [1] M.F. Stamp, CCFE, private communication [2] SOLPS4.3 code: run #1514, A. S. Kukushkin, IO/PWI 9 years of JET operation 3 ITER Q=10 (~1.5 hours of real time) 3 decades of JET, or ~half the time humanity has spent on controlled fusion, in a morning the high resulting material turnover affects tritium retention, material mixing, & layer growth S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 15

16 Material migration: alloying and fuel trapping High wall fluence results in (relatively) high rate of material turn-over surface layer composition can affect sputtering rates [K.Schmid, IPP; R. Doerner, UCSD] Surface evolution depends sensitively on deposition rate, incoming particle energy, and surface temperature complex problem S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 16

17 net erosion yield Be sputtering rate: experimental results: PISCES-B Results suggest that the sputtering rate of re-deposited material has a significantly higher sputtering rate than the bulk atoms [R. Doerner et al., PSI 2012, UCSD] Experiment Prediction 0 Net deposition Be Plasma Concentration Be plasma concentration S. Lisgo / IAEA CRP A+M Data for Light Elements in Fusion Plasmas Page 17

18 Be line ratio Be sputtering rate: experimental results: JET JET ITER-like wall installed for 2011 Be on main wall, W in divertor detailed (ERO) modelling of main chamber Be erosion is underway model refinements required before sputtering yields can be benchmarked [D. Borodin et al., PSI 2012, FZJ] integrated plasma density (m -2 ) S. Lisgo / IAEA CRP A+M Data for Light Elements in Fusion Plasmas Page 18

$molecular fraction SPUTTERING YIELD FRACTION OF BeD [C.$

19 Be MD sputtering rate calculations Molecular dynamics simulations are being performed to refine the codecalculated Be sputtering yields and estimate the molecular fraction SPUTTERING YIELD FRACTION OF BeD [C. Björkas et al, PSI 2012, Helsinki U.] S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 19

Boundary radiation and divertor detachment Need to

order to reduce the heat load on the targets: C and/or N

DETACHMENT ATTACHED PLASMA Low temperature divertor

effects, high neutral particle densities, plasma pressure

20 Boundary radiation and divertor detachment Need to radiate ~75% of the power entering the plasma boundary in order to reduce the heat load on the targets: C and/or N (?), Ne, Ar (seeded) Divertor detachment required DETACHMENT ATTACHED PLASMA Low temperature divertor plasma (< 5 ev) complex plasma chemistry molecular effects, high neutral particle densities, plasma pressure loss S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 20

21 H 2 collisional-radiative model in ADAS Collisional model for hydrogen molecules recently added [F. Guzmán] code framework in place and populated for H 2 with measured/estimated rates experimental benchmarking and extensions to other isotopes are pending DISTRIBUTION OF VIBRATIONAL 25 ev [F. Guzmán, et al, PSI 2012, CEA, U. Strathclyde] S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 21

Parasitic plasma in the sub-divertor Parasitic plasma (n e 10 18 m -3, T e ~ 15 ev) has been observed under the divertor in ASDEX-Upgrade [V. Rohde et al. J. Nucl. Mat.

22 Parasitic plasma in the sub-divertor Parasitic plasma (n e m -3, T e ~ 15 ev) has been observed under the divertor in ASDEX-Upgrade [V. Rohde et al. J. Nucl. Mat (2003) 337] n e scales very strongly with radiation power suggests photo-ionization Need photo-ionisation and photo-dissociation rates parasitic plasma may be an issue in a high duty-cycle device like ITER simulations required [from a slide by M. Shimada] S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 22

be used due to activation issues) atomic

23 Disruption mitigation by massive gas injection Critical for mitigating the effects of disruptions (sudden loss of confinement) Ne probably (Ar likely not to be used due to activation issues) atomic data at high ( massive ) ion density JET MGI [A. Alonso, M. Lehnin, EFDA-JET] S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 23

24 Outline Status of the ITER Project (6 slides) Overview of the ITER device (4 slides) Plasma environment and A/M/PMI processes (11 slides) Relevant ITER diagnostics (4 slides) ITER data management strategy (1 slide) Summary (1 slide) S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 24

day intelligent filtering will be required) UPPER PORT (12 used) EQUATORIAL PORT (6 used) VESSEL WALL (distributed systems)

25 Plasma control: measurements (diagnostic systems) About 40 major diagnostic systems, eventually (extremely well diagnosed) required for machine protection, plasma control, and finally, physics studies (can reach peta-bytes of raw data on a good day intelligent filtering will be required) UPPER PORT (12 used) EQUATORIAL PORT (6 used) VESSEL WALL (distributed systems) DIVERTOR CASSETTES (16 used) DIVERTOR PORT (6 used) S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 25

Divertor Impurity Monitor Visible spectroscopy system for the divertor [JA DA] the objective is to produce 2D information, but limited spatial resolution May be the primary long-term divertor plasma

26 Divertor Impurity Monitor Visible spectroscopy system for the divertor [JA DA] the objective is to produce 2D information, but limited spatial resolution May be the primary long-term divertor plasma diagnostic plasma recycling flux plasma composition (impurities) material influx from the wall (S/XB) plasma conditions (n e, v, T e, T i ) Divertor VUV system also being developed W Also installing a dedicated main chamber spectroscopy system [RF DA] S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 26

Plasma parameters from helium line ratios Ratios of measured line emission from atomic helium have the potential to offer spatially resolved data on n e and T e in the

27 Plasma parameters from helium line ratios Ratios of measured line emission from atomic helium have the potential to offer spatially resolved data on n e and T e in the plasma boundary lots of challenges, including the atomic physics ADAS pju08 He / 728 nm S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 27

28 Diagnostics: Charge Exchange Rec. Spec. (CXRS) CX between diagnostic neutral beam and impurities (C, Be, W, He, N, Ne, Ar) DNB: Diagnostic Neutral Beam (~1.5 MW) 100 kev H 0, 3 s on 20 s off need to identify W lines that are near the CX lines of interest S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 28

29 Outline Status of the ITER Project (6 slides) Overview of the ITER device (4 slides) Plasma environment and A/M/PMI processes (11 slides) Relevant ITER diagnostics (4 slides) ITER data management strategy (1 slide) Summary (1 slide) S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 29

30 ITER A/M/PMI data management strategy Main IO players: Integrated Modelling (IM) and Computer Services (CODAC) discussions/negotiations on how CODAC will support IM have begun Primary IM tool: the ITER Integrated Modelling Analysis Suite, or IMAS Central to IMAS is the Data Model universal API that sits above all of the ITER data served by CODAC represents a single point of entry data tracking (origins, version, etc.) will be part of the Data Model, i.e. selfdocumentation EU-ITM CPO structure may be a good starting point for defining the details of the Data Model, i.e. see the presentation by D. Coster at this meeting S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 30

31 Summary Composition of the ITER plasma fusion reactions plasma facing materials (mixed) impurity seeding for plasma control W emission near CX lines of interest off-normal species The timescale for modeling development H, D, T, He, associated molecules Be, C, W, associated molecules N (?), Ne, Ar O, Fe, Cu, Plasma conditions core (fully ionised, except pellets, NBI, W) T ~ kev, n ~ m -3 boundary / edge T ~ ev, n ~ m -3 Surface interaction data physical + chemical sputtering rates for bulk, re-deposited, and mixed materials (temperature dependence of physical sputtering rates?) ITER A/M/PMI data management efforts are underway, conceptual-level discussions thus far S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June Page 31

Divertor Requirements and Performance in ITER

Divertor Requirements and Performance in ITER M. Sugihara ITER International Team 1 th International Toki Conference Dec. 11-14, 001 Contents Overview of requirement and prediction for divertor performance