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Title: Snowflake divertor configuration studies for NSTX-Upgrade

Abstract

Snowflake divertor experiments in NSTX provide basis for PMI development toward NSTX-Upgrade. Snowflake configuration formation was followed by radiative detachment. Significant reduction of steady-state divertor heat flux observed in snowflake divertor. Impulsive heat loads due to Type I ELMs are partially mitigated in snowflake divertor. Magnetic control of snowflake divertor configuration is being developed. Plasma material interface development is critical for NSTX-U success. Four divertor coils should enable flexibility in boundary shaping and control in NSTX-U. Snowflake divertor experiments in NSTX provide good basis for PMI development in NSTX-Upgrade. FY 2009-2010 snowflake divertor experiments in NSTX: (1) Helped understand control of magnetic properties; (2) Core H-mode confinement unchanged; (3) Core and edge carbon concentration reduced; and (4) Divertor heat flux significantly reduced - (a) Steady-state reduction due to geometry and radiative detachment, (b) Encouraging results for transient heat flux handling, (c) Combined with impurity-seeded radiative divertor. Outlook for snowflake divertor in NSTX-Upgrade: (1) 2D fluid modeling of snowflake divertor properties scaling - (a) Edge and divertor transport, radiation, detachment threshold, (b) Compatibility with cryo-pump and lithium conditioning; (2) Magnetic control development; and (3) PFC development - PFC alignment and PFC material choice.

Authors:
Publication Date:
Research Org.:
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1035601
Report Number(s):
LLNL-CONF-514131
TRN: US1201161
DOE Contract Number:  
W-7405-ENG-48
Resource Type:
Conference
Resource Relation:
Conference: Presented at: 53rd Annual Meeting of the APS Division of Plasma Physics, Salt Lake City, UT, United States, Nov 14 - Nov 18, 2011
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; ALIGNMENT; CARBON; COMPATIBILITY; CONFIGURATION; CONFINEMENT; DIVERTORS; FLEXIBILITY; GEOMETRY; HEAT FLUX; LITHIUM; MAGNETIC PROPERTIES; PHYSICS; PLASMA; SIMULATION; TRANSIENTS; TRANSPORT

Citation Formats

Soukhanovskii, V A. Snowflake divertor configuration studies for NSTX-Upgrade. United States: N. p., 2011. Web.
Soukhanovskii, V A. Snowflake divertor configuration studies for NSTX-Upgrade. United States.
Soukhanovskii, V A. Sat . "Snowflake divertor configuration studies for NSTX-Upgrade". United States. https://www.osti.gov/servlets/purl/1035601.
@article{osti_1035601,
title = {Snowflake divertor configuration studies for NSTX-Upgrade},
author = {Soukhanovskii, V A},
abstractNote = {Snowflake divertor experiments in NSTX provide basis for PMI development toward NSTX-Upgrade. Snowflake configuration formation was followed by radiative detachment. Significant reduction of steady-state divertor heat flux observed in snowflake divertor. Impulsive heat loads due to Type I ELMs are partially mitigated in snowflake divertor. Magnetic control of snowflake divertor configuration is being developed. Plasma material interface development is critical for NSTX-U success. Four divertor coils should enable flexibility in boundary shaping and control in NSTX-U. Snowflake divertor experiments in NSTX provide good basis for PMI development in NSTX-Upgrade. FY 2009-2010 snowflake divertor experiments in NSTX: (1) Helped understand control of magnetic properties; (2) Core H-mode confinement unchanged; (3) Core and edge carbon concentration reduced; and (4) Divertor heat flux significantly reduced - (a) Steady-state reduction due to geometry and radiative detachment, (b) Encouraging results for transient heat flux handling, (c) Combined with impurity-seeded radiative divertor. Outlook for snowflake divertor in NSTX-Upgrade: (1) 2D fluid modeling of snowflake divertor properties scaling - (a) Edge and divertor transport, radiation, detachment threshold, (b) Compatibility with cryo-pump and lithium conditioning; (2) Magnetic control development; and (3) PFC development - PFC alignment and PFC material choice.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2011},
month = {11}
}

Conference:
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