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 20-22 Page 1
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 20-22 Page 2
Current status of the ITER platform S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June 20-22 Page 3
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 20-22 Page 4
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 20-22 Page 5
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 15622 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 20-22 Page 6
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 20-22 Page 7
The ITER tokamak R ~ 6 m h ~ 29 m S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June 20-22 Page 8
Overview of major systems S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June 20-22 Page 9
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 20-22 Page 10
Plasma facing materials Why this mix of materials? ATOMIC NUMBER (ALLOWED MELTING CORE / SUBLIMATION CONCENTRATION POINT @ 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 20-22 Page 11
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 20-22 Page 12
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
Predicted conditions at the outer divertor target plate S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June 20-22 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 WITH JET (2000-2008, campaigns C1-C19) No. Pulses Time in Diverted Phase (hours) Outer Divertor Ion Fluence JET 13466 40.5 ~5x10 27 [1] ITER (Q=10) 1 0.15 ~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 pulses @ 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 20-22 Page 15
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 20-22 Page 16
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 0.0025 [R. Doerner et al., PSI 2012, UCSD] 0.002 0.0015 0.001 0.0005 Experiment Prediction 0 Net deposition -0.0005 10-5 0.0001 0.001 0.01 0.1 Be Plasma Concentration Be plasma concentration S. Lisgo / IAEA CRP A+M Data for Light Elements in Fusion Plasmas Page 17
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
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 20-22 Page 19
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 20-22 Page 20
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 STATES @ 25 ev [F. Guzmán, et al, PSI 2012, CEA, U. Strathclyde] S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June 20-22 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. 313-316 (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 20-22 Page 22
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 20-22 Page 23
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 20-22 Page 24
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 20-22 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 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 20-22 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 plasma boundary lots of challenges, including the atomic physics ADAS pju08 He +0 668 / 728 nm S. W. Lisgo / IAEA A/M/PMI Data Planning Meeting / Vienna / June 20-22 Page 27
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 20-22 Page 28
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 20-22 Page 29
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 20-22 Page 30
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 ~ 0.2 20 kev, n ~ 10 20 m -3 boundary / edge T ~ 0.1 200 ev, n ~ 10 18 10 21 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 20-22 Page 31