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Title: Fusion Energy Sciences FY 2017 Joint Research Target (JRT) Summary Milestone Report

Abstract

In support of the 2017 JRT, the DIII-D, NSTX-U and C-Mod teams performed coordinated research, focused on the subjects of dissipative divertor physics and divertor heat flux footprints. As evident in this report, good progress was made on many fronts toward assembling informed pictures of the plasma physics. The teams chose research topics that would best utilize the unique capabilities of DIII-D, NSTX and C-Mod – access to interesting divertor magnetic configurations and geometries, excellent diagnostic sets and extended parameter regimes. The research took advantage of dedicated experimental investigations on DIII-D and archived data analyses from NSTX and C-Mod – all targeted to address keys questions for tokamak power exhaust handling. DIII-D dedicated significant run time to support the 2017 JRT. This included coordinated experiments to investigate an NSTX-like, high flux expansion divertor configuration to compare its detachment response to that seen in NSTX. DIII-D implemented divertor diagnostic upgrades as well and operated with a ‘small angle slot’ divertor to investigate this ‘closed’ divertor configuration. Follow-on experiments are planned to utilize these tools. Analysis of archived data from NSTX and C-Mod was designed to exploit the wealth of information that had been collected during prior experimental campaigns. These investigations includedmore » the influence of high poloidal flux expansion on detachment onset (NSTX), magnetic flux balance dependencies of the power exhaust footprints (NSTX and C-Mod), power exhaust channel widths at poloidal magnetic fields greater than 1 Tesla, in the I-mode confinement regime and in response to divertor nitrogen seeding (C-Mod).« less

Authors:
 [1];  [1];  [2]
  1. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
  2. Massachusetts Inst. of Technology (MIT), Boston, MA (United States)
Publication Date:
Research Org.:
USDOE Office of Science (SC), Washington, D.C. (United States). Fusion Energy Sciences (FES)
Sponsoring Org.:
USDOE Office of Science (SC), Fusion Energy Sciences (FES) (SC-24)
OSTI Identifier:
1471200
Report Number(s):
DOE-1471200
TRN: US1902858
DOE Contract Number:  
AC52-07NA27344; FC02-99ER54512; AC02-09CH11466; FC02-04ER54698
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY

Citation Formats

Allen, S., Soukhanovskii, Vlad, and LaBombard, Brian. Fusion Energy Sciences FY 2017 Joint Research Target (JRT) Summary Milestone Report. United States: N. p., 2017. Web. doi:10.2172/1471200.
Allen, S., Soukhanovskii, Vlad, & LaBombard, Brian. Fusion Energy Sciences FY 2017 Joint Research Target (JRT) Summary Milestone Report. United States. doi:10.2172/1471200.
Allen, S., Soukhanovskii, Vlad, and LaBombard, Brian. Sun . "Fusion Energy Sciences FY 2017 Joint Research Target (JRT) Summary Milestone Report". United States. doi:10.2172/1471200. https://www.osti.gov/servlets/purl/1471200.
@article{osti_1471200,
title = {Fusion Energy Sciences FY 2017 Joint Research Target (JRT) Summary Milestone Report},
author = {Allen, S. and Soukhanovskii, Vlad and LaBombard, Brian},
abstractNote = {In support of the 2017 JRT, the DIII-D, NSTX-U and C-Mod teams performed coordinated research, focused on the subjects of dissipative divertor physics and divertor heat flux footprints. As evident in this report, good progress was made on many fronts toward assembling informed pictures of the plasma physics. The teams chose research topics that would best utilize the unique capabilities of DIII-D, NSTX and C-Mod – access to interesting divertor magnetic configurations and geometries, excellent diagnostic sets and extended parameter regimes. The research took advantage of dedicated experimental investigations on DIII-D and archived data analyses from NSTX and C-Mod – all targeted to address keys questions for tokamak power exhaust handling. DIII-D dedicated significant run time to support the 2017 JRT. This included coordinated experiments to investigate an NSTX-like, high flux expansion divertor configuration to compare its detachment response to that seen in NSTX. DIII-D implemented divertor diagnostic upgrades as well and operated with a ‘small angle slot’ divertor to investigate this ‘closed’ divertor configuration. Follow-on experiments are planned to utilize these tools. Analysis of archived data from NSTX and C-Mod was designed to exploit the wealth of information that had been collected during prior experimental campaigns. These investigations included the influence of high poloidal flux expansion on detachment onset (NSTX), magnetic flux balance dependencies of the power exhaust footprints (NSTX and C-Mod), power exhaust channel widths at poloidal magnetic fields greater than 1 Tesla, in the I-mode confinement regime and in response to divertor nitrogen seeding (C-Mod).},
doi = {10.2172/1471200},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2017},
month = {12}
}