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

2. http://efdasql.ipp.mpg.de/divsol user : divsol password : Mitigat_elm1 Max-Planck-institut fur Plasmaphysik, D- 85748 Garching bei Munchen,Germany May 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. High priority research tasks 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)