Published December 1999
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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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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
- Notes
- 12 refs, 6 figs, 2 tabs
- Collaborations
- ITER Joint Central Team; ITER Home Teams; ITER Disruption Group; Plasma Control Group; MHD Expert Group
- Secondary number(s)
- ITER--3