Powerful 160-keV neutral deuterium beam injector for application in fusion research

Journal Article · Tue Jul 01 00:00:00 EDT 1986 · Rev. Sci. Instrum.; (United States)

DOI:https://doi.org/10.1063/1.1138640· OSTI ID:5791510

Fumelli, M; Bayetti, P; Becherer, R; Bottiglioni, F; Desmons, M; Jequier, F; Pamela, J; Raimbault, P; Valckx, F P.G.

A 160-keV neutral deuterium beam injector has been developed for plasma heating in JET (Joint European Torus) fusion experiment. This injector has been reliably operated at 5.9-MW extracted deuterium ion beam power (37-A, 160-keV ion beam) and 5-s pulse duration. The neutral beam power was 1.75 MW corresponding to an overall neutral injector power efficiency of 30%. The beam divergence was 0.6/sup 0/. The ion beam was accelerated with a three-grid multiaperture system (aperture diameter phi = 11 mm). The accelerating gap length was 24 mm. The extracted deuterium ion current density amounted to 150 mA/cm/sup 2/. Grid and source body power loadings were acceptable for quasi-steady-state operation.

• Research Organization: Association Euratom-CEA sur la Fusion, Centre d'Etudes Nucleaires, B. P. 6, 92265, Fontenay-aux-Roses, France
• OSTI ID: 5791510
• Journal Information: Rev. Sci. Instrum.; (United States), Vol. 57:7
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
DEUTERIUM
NEUTRAL BEAM SOURCES
JET TOKAMAK
BEAM CURRENTS
OPERATION
BEAM EXTRACTION
CURRENT DENSITY
EXPERIMENTAL DATA
FOCUSING
KEV RANGE 10-100
NEUTRAL ATOM BEAM INJECTION
PLASMA BEAM INJECTION
PULSES
RELIABILITY
BEAM INJECTION
CURRENTS
DATA
ENERGY RANGE
HYDROGEN ISOTOPES
INFORMATION
ISOTOPES
KEV RANGE
LIGHT NUCLEI
NUCLEI
NUMERICAL DATA
ODD-ODD NUCLEI
STABLE ISOTOPES
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
700205* - Fusion Power Plant Technology- Fuel
Heating
& Injection Systems