Introduction of 9th ITPA Meeting, Divertor & SOL and PEDESTAL

1. Introduction of 9th ITPA Meeting, Divertor & SOL and PEDESTAL Jiansheng Hu 2006-6-14

2. http://efdasql.ipp.mpg.de/divsoluser : divsol password : Mitigat_elm1Max-Planck-institut fur Plasmaphysik, D-85748 Garching bei Munchen,GermanyMay 7-10,2007

3. Topics • D retention and removal • PFCs Materials • Design review for ITER • ELM • Modeling

4. D retention and removal • Effect of C ions on D retention in W • Depth-profiling and thermal desorption of hydrogen isotopes for JT-60U tiles • The physics of long range retention in different materials • Effect of co-deposited layers the migration pattern of D into CFC • modelling of ion-driven retention of D in W • Long-range retention in Molybdenum • A Dynamic Model for Deuterium Retention in Molybdenum • D retention with Mo PFCs in C-Mod • D retention with C PFCs in JET • D inventory in ASDEX-Upgrade • D retention in impurity seeded long pulse Tore Supra discharges • investigation of dynamic retention under near-saturated wall condition • Ion beam analysis of JET Be castellated limiter tiles • On carbon deposition in the first wall gaps • Effects of ICRF conditioning on the first wall in LHD • Wall conditionings for hydrogen removal on metal walls in EAST

5. Design review for ITER • ITER Wall conditioning design review committee report • TER first-wall strategy design review committee report • ITER PFC heat loads design review committee report • Scalings of q_parallel to ITER • Physics assumptions that determine the T limit in ITER • Operational sequence of ITER for H, D, and DT phases

6. PFCs Materials • Hydrocarbon spectroscopy in JET (mainly the effect of detachment) • Carbon erosion and transport in ASDEX Upgrade • Open issues and programme implications of the ITER-like wall experiment • Initial AUG operation with 100 % tungsten PFCs • Erosion and deposition of C in Pilot • QMB studies of material migration in the JET sub-divertor region • Application of optical technique for in situ surface analysis of carbon tiles

7. ELM • Measuremenst of power deposition during ELMs in JET and ASDEX Upgrade • ELM-wall interaction • Divertor plasma-surface interaction and induced radiation under large ELM impact • ELM erosion of PFCs in JET with subsequent material migration • Fast response of the divertor plasma and PWI at ELMs in JT-60U • ELM suppression with Magnetic Perturbations in DIII-D • ELM control using external magnetic perturbation fields on JET • MAST ELM mitigation experiments using Error Field correction coils • Current state of pellet pacing ELM control and its prospects for ITER

8. Modeling 1 • UEDGE modeling of ASDEX-Upgrade and DIII-D • Pedestal ionization profiles on MAST from OSM-Eirene • Status of kinetic neutral modeling of pedestal fueling on Alcator C-Mod • Integrated Modeling of Impurity Seeded JET and ITER Discharges • New version of B2SOLPS5.0 and simulations of H-regimes • Interpretive transport simulations of the edge region with UEDGE • Overview of "plasma reconstruction" modeling • Presentation of the Tokam-3D code • Comparison of AUG and DIII-D SOL parameters using the ITPA database

9. Modeling 2 • Comparisons of SOLPS, UEDGE and EDGE2D • SOLPS5.0 and SOLDOR/NEUT2D modeling of JT-60U discharge • Simulating detachment in ASDEX Upgrade, TCV, and JET • BIT1-SOLPS comparisons • Fluid modeling of the far SOL region • discrepancies between modeling and experiment • Improvements to the wall model in B2.5: coatings and layers • Transfer of SOLPS4.2 ITER simulations to SOLPS5.1 • New physics options in the B2-Eirene modeling package for ITER • Current status on ITER divertor modeling

10. Improve measurements & understanding of plasma transport to targets and walls to better predict heat loads and effects on the core Code-code comparisons with no drifts (✓) New code goal needed ITER neutral density benchmarking of model physics to current experiments (underway) Exploration of the role of radial transport in driving SOL flows (✓) can be replaced Understand the effect of ELMs/disruptions on divertor and first wall structures Development of more precise measurements of where power goes in disruptions/ELMs (✓) Update specification to ITER of power levels and areas of deposition during ELMs and disruptions (Loarte and other papers) Improve understanding of Tritium retention and development of efficient T removal methods. Compare tile-side D retention level across tokamaks (✓) Replace w/comparison of post-mortem and shot-integrated studies? Characterize macroscopic D retention across tokamaks and laboratory expts (co-deposition and long-range studies in progress) Comparison of D/T removal techniques for all-carbon PFC tokamaks (Initial comparison done) Something on O cleaning? Understand how conditioning & operational techniques can be scaled (or not) to future devices Compare startup/rampdown experience across experiments and evaluate the influence of limiter configuration on SOL properties (✓, Done for JET, C-Mod, TS) Implications of a metal wall (no coating) for startup, fuel retention, density control and core impurity levels (underway but 1st step done) High priority research tasks