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Title: RESEARCH PROGRESS AND HARDWARE SYSTEMS AT DIII-D

Abstract

OAK-B135 During the last two years significant progress has been made in the scientific understanding of DIII-D plasmas. Much of this progress has been enabled by the addition of new hardware systems. The electron cyclotron (EC) system has been upgraded from 3 MW to 6 MW, by adding three 1 MW gyrotrons with diamond windows and three steerable launchers (PPPL). The new gyrotrons have been tested to 1.0 MW for 5 s. The system has been used to control the 3/2 and 2/1 neoclassical tearing modes and to locally heat the plasma and thereby indirectly control the current density. Electron cyclotron current drive ECCD has been used to directly affect the current density. A Li-beam diagnostic has been brought on-line for measuring the edge current density using Zeeman splitting. A set of 12 coils (1-coils), consisting of six picture frame coils each above and below the midplane, with a capability of 7 kA for 10 s has been installed inside the DIII-D vessel. These coils, along with the existing six C-coils, are used to apply non-axisymmetric fields to the plasma for both exciting and controlling plasma instabilities. The DIII-D digital plasma control system is now used to not just controlmore » the shape and location of the plasma but also the electron temperature, density, the NTMs, RWMs, plasma beta and disruption mitigation. Plasma disruption experiments are extended to mitigation of real time detected disruptions on DIII-D.« less

Authors:
Publication Date:
Research Org.:
General Atomics, San Diego, CA (United States)
Sponsoring Org.:
(US)
OSTI Identifier:
823594
Report Number(s):
GA-A24478
TRN: US0401781
DOE Contract Number:  
AC03-99ER54463
Resource Type:
Conference
Resource Relation:
Conference: 20th IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, SAN DIEGO, CA (US), 10/14/2003--10/17/2003; Other Information: TO BE PUBLISHED IN FUSION SCIENCE AND TECHNOLOGY; PBD: 1 Oct 2003
Country of Publication:
United States
Language:
English
Subject:
43 PARTICLE ACCELERATORS; CONTROL SYSTEMS; CURRENT DENSITY; CYCLOTRONS; DIAMONDS; DOUBLET-3 DEVICE; ELECTRON TEMPERATURE; ELECTRONS; MICROWAVE AMPLIFIERS; MITIGATION; PLASMA; PLASMA DISRUPTION; SHAPE; WINDOWS

Citation Formats

PETERSEN, P I, and THE DIII-D TEAM. RESEARCH PROGRESS AND HARDWARE SYSTEMS AT DIII-D. United States: N. p., 2003. Web.
PETERSEN, P I, & THE DIII-D TEAM. RESEARCH PROGRESS AND HARDWARE SYSTEMS AT DIII-D. United States.
PETERSEN, P I, and THE DIII-D TEAM. 2003. "RESEARCH PROGRESS AND HARDWARE SYSTEMS AT DIII-D". United States. https://www.osti.gov/servlets/purl/823594.
@article{osti_823594,
title = {RESEARCH PROGRESS AND HARDWARE SYSTEMS AT DIII-D},
author = {PETERSEN, P I and THE DIII-D TEAM},
abstractNote = {OAK-B135 During the last two years significant progress has been made in the scientific understanding of DIII-D plasmas. Much of this progress has been enabled by the addition of new hardware systems. The electron cyclotron (EC) system has been upgraded from 3 MW to 6 MW, by adding three 1 MW gyrotrons with diamond windows and three steerable launchers (PPPL). The new gyrotrons have been tested to 1.0 MW for 5 s. The system has been used to control the 3/2 and 2/1 neoclassical tearing modes and to locally heat the plasma and thereby indirectly control the current density. Electron cyclotron current drive ECCD has been used to directly affect the current density. A Li-beam diagnostic has been brought on-line for measuring the edge current density using Zeeman splitting. A set of 12 coils (1-coils), consisting of six picture frame coils each above and below the midplane, with a capability of 7 kA for 10 s has been installed inside the DIII-D vessel. These coils, along with the existing six C-coils, are used to apply non-axisymmetric fields to the plasma for both exciting and controlling plasma instabilities. The DIII-D digital plasma control system is now used to not just control the shape and location of the plasma but also the electron temperature, density, the NTMs, RWMs, plasma beta and disruption mitigation. Plasma disruption experiments are extended to mitigation of real time detected disruptions on DIII-D.},
doi = {},
url = {https://www.osti.gov/biblio/823594}, journal = {},
number = ,
volume = ,
place = {United States},
year = {2003},
month = {10}
}

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