Plasma-surface interaction, scrape-off layer and divertor physics; Implications for ITER

Lipschultz, B.*; Asakura, Nobuyuki; Bonnin, X.*; Coster, D. P.*; Counsell, G.*; Doerner, R.*; Dux, R.*; Federici, G.*; Fenstermacher, M. E.*; Fundamenski, W.*; Ghendrih, P.*; Herrmann, A.*; Hu, J.*; Kallenbach, A.*; Krasheninnikov, S.*; Krieger, K.*; Kirnev, G.*; Kreter, A.*; Kukushkin, A. S.*; Kurnaev, V.*; LaBombard, B.*; Li, J.*; Lisgo, S.*; Loarte, A.*; Nakano, Tomohide; Neu, R.*; Ono, Noriyasu*; Pacher, H.*; Paley, J.*; Pan, Y.*; Pautasso, G.*; Philipps, V.*; Riccardo, V.*; Rohde, V.*; Roth, J.*; Rudakov, D.*; Stangeby, P. C.*; Takamura, Shuichi*; Tanabe, Tetsuo*; Tsitrone, E.*; Whyte, D.*; Yang, Y.*; Zhu, S.*

The work of the ITPA SOL/divertor group is reviewed. The high-n nature of ELMs has been elucidated and new measurements have determined that they carry 10-20% of the ELM energy to the far SOL with implications for ITER limiters and the upper divertor. Analysis of ELM measurements imply that the ELM continuously loses energy as it travels across the SOL. The prediction of ITER divertor disruption power loads have been reduced as a result of finding that the divertor footprint broadens during the thermal quench and that the plasma can lose up to 80% of its thermal energy before the thermal quench (not for VDEs or ITBs). Disruption mitigation through massive gas puffing has been successful at reducing divertor heat loads but estimates of the effect on the main chamber walls indicate 10s of kG of Be would be melted/mitigation. Long-pulse studies have shown that the fraction of injected gas that can be recovered after a discharge decreases with discharge length. The use of mixed materials gives rise to a number of potential processes.