Update of neutral beams for ITER

Journal Article · Thu Aug 20 04:00:00 EDT 1998 · AIP Conference Proceedings

DOI:https://doi.org/10.1063/1.56352· OSTI ID:21199171

Hemsworth, R S; Di Pietro, E ^[1]; Inoue, T; Krylov, A ^[2]; Okumura, Y ^[3]; Tanii, M; Watson, M ^[4]

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1. Association EURATOM--C. E. A., C. E. Cadarache, 13108 St. Paul-lez-Durance (France)
2. ITER Joint Central Team, Naka (Japan)
3. JAERI, Naka (Japan)
4. JET Joint Undertaking, Abingdon (United Kingdom)

The design of the neutral beam injection heating and current drive system for the International Tokamak Experimental Reactor is based on the neutralisation of accelerated D{sup -} ions. This paper describes changes in the design which have occurred since it was presented at the first of these symposia (1) and outlines the negative ion beam source proposed as the basis of the ITER diagnostic neutral beam injector. The proposed NBI system consists of three negative ion based neutral injectors, delivering a total of 50 MW of 1 MeV D{sup 0} to the ITER plasma for pulse lengths of >10,000 s. The diagnostic beam system consists of a single beamline delivering a 5 MW modulated beam of 125 keV H{sup 0} to the ITER plasma.

• OSTI ID: 21199171
• Journal Information: AIP Conference Proceedings, Journal Name: AIP Conference Proceedings Journal Issue: 1 Vol. 439; ISSN APCPCS; ISSN 0094-243X
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
ANIONS
BEAM INJECTION HEATING
BEAM-PLASMA SYSTEMS
DESIGN
DEUTERIUM IONS
DEUTERON SOURCES
ION BEAMS
ION SOURCES
ITER TOKAMAK
KEV RANGE
MEV RANGE
NEUTRAL ATOM BEAM INJECTION
PLASMA
PLASMA DIAGNOSTICS
PULSES