Published December 1999 | Version v1
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Operation and control of ITER plasmas

Description

Features incorporated in the design of the International Thermonuclear Experimental Reactor (ITER) tokamak and its ancillary and plasma diagnostic systems that will facilitate operation and control of ignited and/or high-Q DT plasmas are presented. Control methods based upon straight-forward extrapolation of techniques employed in the present generation of tokamaks are found to be adequate and effective for DT plasma control with burn durations of ≥1000 s. Examples of simulations of key plasma control functions including magnetic configuration control and fusion burn (power) control are given. The prospects for the creation and control of steady-state plasmas sustained by non-inductive current drive are also discussed. (author)

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Part of:
Fusion energy 1998. Proceedings. V. 1-4

Additional details

Publishing Information

Imprint Title
Fusion energy 1998. Proceedings. V. 1-4
Imprint Pagination
1721 p.
Journal Issue
no. 1/P
Series
C and S papers series
Journal Page Range
v. 3 p. 947-955
ISSN
1563-0153
Report number
IAEA-CSP--1/P

Conference

Title
17. IAEA fusion energy conference
Dates
18-24 Oct 1998
Place
Yokohama (Japan)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
31011406
Subject category
S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
ITER TOKAMAK; MEETINGS; REACTOR OPERATION; REACTOR SHUTDOWN; REACTOR START-UP
Descriptors DEC
CLOSED PLASMA DEVICES; OPERATION; SHUTDOWN; START-UP; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTORS; TOKAMAK DEVICES; TOKAMAK TYPE REACTORS

Optional Information