Development testing of the U. S. common long pulse source at 120 kV
Journal Article
·
· Rev. Sci. Instrum.; (United States)
The U. S. magnetic fusion energy program has developed a single design, long-pulse neutral beam source for TFTR, MFTF-B, and DIII-D. The arc is a very compact axial magnetic line cusp. The accelerator is an actively cooled tetrode with water-cooled grid tubes of shaped molybdenum forming ''slot'' beamlets. DIII-D and MFTF-B configurations have an 80-kV accelerator gap, with a 12 x 18 cm aperture, and a 10-m ''module'' focus. TFTR modules are unfocused, with a 120-kV gap and 12 x 43-cm mask. The first CLPS was tested in the TFTR configuration, at 120 kV, 2s. Optimum current was 73 A, or 1.76 ..mu..pervs (deuterium), with 80%--85% atomic fraction. Optimum divergence of ions plus neutrals was 0.4/sup 0/ parallel to the slots, and 0.7/sup 0/ perpendicular to the slots (1/e half-angle). The combination of an axial cusp magnetic bucket and slot accelerator apertures gives the common long pulse source about twice the beam power per unit cross section of other long pulse sources, plus lower divergence in the direction parallel to the slots.
- Research Organization:
- Lawrence Berkeley Laboratory, Berkeley, California 94720
- OSTI ID:
- 6729745
- Journal Information:
- Rev. Sci. Instrum.; (United States), Journal Name: Rev. Sci. Instrum.; (United States) Vol. 59:11; ISSN RSINA
- Country of Publication:
- United States
- Language:
- English
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DEVELOPMENT TESTING OF THE U.S. COMMON LONG PULSE SOURCE AT 120KV
Prototype testing for the US common long pulse neutral beam source
120-kV testing of a 10 x 40-cm prototype of the U. S. common long pulse neutral beam source
Journal Article
·
Mon Nov 30 23:00:00 EST 1987
· Review of Scientific Instruments
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OSTI ID:919665
Prototype testing for the US common long pulse neutral beam source
Conference
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Thu Oct 31 23:00:00 EST 1985
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OSTI ID:6171330
120-kV testing of a 10 x 40-cm prototype of the U. S. common long pulse neutral beam source
Journal Article
·
Fri Oct 31 23:00:00 EST 1986
· Rev. Sci. Instrum.; (United States)
·
OSTI ID:5207247
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700205* -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
BEAM INJECTION
BEAM INJECTION HEATING
DESIGN
HEATING
NEUTRAL ATOM BEAM INJECTION
NEUTRAL BEAM SOURCES
OPERATION
PERFORMANCE TESTING
PLASMA HEATING
PULSES
RESEARCH PROGRAMS
TEST FACILITIES
TESTING
700205* -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
BEAM INJECTION
BEAM INJECTION HEATING
DESIGN
HEATING
NEUTRAL ATOM BEAM INJECTION
NEUTRAL BEAM SOURCES
OPERATION
PERFORMANCE TESTING
PLASMA HEATING
PULSES
RESEARCH PROGRAMS
TEST FACILITIES
TESTING