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Taming the plasma-material interface with the “snowflake” divertor

Supported by . Taming the plasma-material interface with the “snowflake” divertor. College W&M Colorado Sch Mines Columbia U CompX General Atomics INEL Johns Hopkins U LANL LLNL Lodestar MIT Nova Photonics New York U Old Dominion U ORNL PPPL PSI Princeton U Purdue U SNL

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Taming the plasma-material interface with the “snowflake” divertor

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  1. Supported by Taming the plasma-material interface with the “snowflake” divertor College W&M Colorado Sch Mines Columbia U CompX General Atomics INEL Johns Hopkins U LANL LLNL Lodestar MIT Nova Photonics New York U Old Dominion U ORNL PPPL PSI Princeton U Purdue U SNL Think Tank, Inc. UC Davis UC Irvine UCLA UCSD U Colorado U Illinois U Maryland U Rochester U Washington U Wisconsin Culham Sci Ctr U St. Andrews York U Chubu U Fukui U Hiroshima U Hyogo U Kyoto U Kyushu U Kyushu Tokai U NIFS Niigata U U Tokyo JAEA Hebrew U Ioffe Inst RRC Kurchatov Inst TRINITI KBSI KAIST POSTECH ASIPP ENEA, Frascati CEA, Cadarache IPP, Jülich IPP, Garching ASCR, Czech Rep U Quebec V. A. Soukhanovskii, LLNL and NSTX Team Proposal for APS DPP 2010 Meeting Invited Talk Nomination NSTX Physics Meeting Princeton, NJ 3 May 2010

  2. Outline • Motivation: PMI challenge • “Snowflake” divertor configuration idea by D. D. Ryutov • Analytic theory and numerical modeling • NSTX results in hand • Magnetic properties (area expansion, angles, SOL volume) • Actual NSTX equilibria and ISOLVER models • Magnetic control (SP control, X-point control with PCS) • Main results: divertor peak heat flux reduction, impurity reduction • Other results: pedestal stability, core confinement, divertor properties, compatibility with pumping scenarios, preliminary turbulence characteristics • Results to be obtained • turbulence and blobs, heat flux scaling, SOL flows, impurity sources, ELM control, ion X-point loss • UEDGE modeling of radiation and edge/SOL transport • Projections for future devices (NSTX-U, ST-CTF)

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