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Title: Non-Inductive Current Drive Modeling Extending Advanced Tokamak Operation to Steady State

Abstract

A critical issue for sustaining high performance, negative central shear (NCS) discharges is the ability to maintain current distributions that are maximum off axis. Sustaining such hollow current profiles in steady state requires the use of non-inductively driven current sources. On the DIII-D experiment, a combination of neutral beam current drive (NBCD) and bootstrap current have been used to create transient NCS discharges. The electron cyclotron heating (ECH) and current drive (ECCD) system is currently being upgraded from three gyrotrons to six to provide more than 3MW of absorbed power in long-pulse operation to help sustain the required off-axis current drive. This upgrade SuPporrs the long range goal of DIII-D to sustain high performance discharges with high values of normalized {beta}, {beta}{sub n} = {beta}/(I{sub p}/aB{sub T}), confinement enhancement factor, H, and neutron production rates while utilizing bootstrap current fraction, f{sub bs}, in excess of 50%. At these high performance levels, the likelihood of onset of MHD modes that spoil confinement indicates the need to control plasma profiles if we are to extend this operation to long pulse or steady state. To investigate the effectiveness of the EC system and to explore operating scenarios to sustain these discharges, we usemore » time-dependent simulations of the equilibrium, transport and stability. We explore methods to directly alter the safety factor profile, q, through direct current drive or by localized electron heating to modify the bootstrap current profile. Time dependent simulations using both experimentally determined [1] and theory-based [2] energy transport models have been done. Here, we report on simulations exploring parametric dependencies of the heating, current drive, and profiles that affect our ability to sustain stable discharges.« less

Authors:
; ; ; ; ; ; ;
Publication Date:
Research Org.:
Lawrence Livermore National Lab., CA (US)
Sponsoring Org.:
USDOE Office of Defense Programs (DP) (US)
OSTI Identifier:
792815
Report Number(s):
UCRL-JC-137397
TRN: US0300614
DOE Contract Number:  
W-7405-Eng-48
Resource Type:
Conference
Resource Relation:
Conference: 27th European Physical Society Conference on Controlled Fusion and Plasma Physics, Budapest (HU), 06/12/2000--06/16/2000; Other Information: PBD: 6 Jun 2000
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; BEAM CURRENTS; BOOTSTRAP CURRENT; DIRECT CURRENT; DOUBLET-3 DEVICE; ELECTRONS; HEATING; MICROWAVE AMPLIFIERS; NON-INDUCTIVE CURRENT DRIVE; PHYSICS; SHEAR; TRANSPORT

Citation Formats

Casper, T A, Lodestro, L L, Pearlstein, L D, Porter, G D, Murakami, M, Lao, L L, Lin-Lui, Y R, and John, H E. Non-Inductive Current Drive Modeling Extending Advanced Tokamak Operation to Steady State. United States: N. p., 2000. Web.
Casper, T A, Lodestro, L L, Pearlstein, L D, Porter, G D, Murakami, M, Lao, L L, Lin-Lui, Y R, & John, H E. Non-Inductive Current Drive Modeling Extending Advanced Tokamak Operation to Steady State. United States.
Casper, T A, Lodestro, L L, Pearlstein, L D, Porter, G D, Murakami, M, Lao, L L, Lin-Lui, Y R, and John, H E. Tue . "Non-Inductive Current Drive Modeling Extending Advanced Tokamak Operation to Steady State". United States. https://www.osti.gov/servlets/purl/792815.
@article{osti_792815,
title = {Non-Inductive Current Drive Modeling Extending Advanced Tokamak Operation to Steady State},
author = {Casper, T A and Lodestro, L L and Pearlstein, L D and Porter, G D and Murakami, M and Lao, L L and Lin-Lui, Y R and John, H E},
abstractNote = {A critical issue for sustaining high performance, negative central shear (NCS) discharges is the ability to maintain current distributions that are maximum off axis. Sustaining such hollow current profiles in steady state requires the use of non-inductively driven current sources. On the DIII-D experiment, a combination of neutral beam current drive (NBCD) and bootstrap current have been used to create transient NCS discharges. The electron cyclotron heating (ECH) and current drive (ECCD) system is currently being upgraded from three gyrotrons to six to provide more than 3MW of absorbed power in long-pulse operation to help sustain the required off-axis current drive. This upgrade SuPporrs the long range goal of DIII-D to sustain high performance discharges with high values of normalized {beta}, {beta}{sub n} = {beta}/(I{sub p}/aB{sub T}), confinement enhancement factor, H, and neutron production rates while utilizing bootstrap current fraction, f{sub bs}, in excess of 50%. At these high performance levels, the likelihood of onset of MHD modes that spoil confinement indicates the need to control plasma profiles if we are to extend this operation to long pulse or steady state. To investigate the effectiveness of the EC system and to explore operating scenarios to sustain these discharges, we use time-dependent simulations of the equilibrium, transport and stability. We explore methods to directly alter the safety factor profile, q, through direct current drive or by localized electron heating to modify the bootstrap current profile. Time dependent simulations using both experimentally determined [1] and theory-based [2] energy transport models have been done. Here, we report on simulations exploring parametric dependencies of the heating, current drive, and profiles that affect our ability to sustain stable discharges.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2000},
month = {6}
}

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