Modeling activities on the negative-ion-based Neutral Beam Injectors of the Large Helical Device
Journal Article
·
· AIP Conference Proceedings
- Consorzio RFX, Associazione Euratom-ENEA sulla Fusione, Corso Stati Uniti 4, 35127 Padova (Italy)
- INFN, Laboratori Nazionali di Legnaro, V.le dell'Universita 2, 35020 Legnaro (Italy)
- National Institute for Fusion Science, 322-6 Oroshi-cho, Toki 509-5292 (Japan)
At the National Institute for Fusion Science (NIFS) large-scaled negative ion sources have been widely used for the Neutral Beam Injectors (NBIs) mounted on the Large Helical Device (LHD), which is the world-largest superconducting helical system. These injectors have achieved outstanding performances in terms of beam energy, negative-ion current and optics, and represent a reference for the development of heating and current drive NBIs for ITER.In the framework of the support activities for the ITER NBIs, the PRIMA test facility, which includes a RF-drive ion source with 100 keV accelerator (SPIDER) and a complete 1 MeV Neutral Beam system (MITICA) is under construction at Consorzio RFX in Padova.An experimental validation of the codes has been undertaken in order to prove the accuracy of the simulations and the soundness of the SPIDER and MITICA design. To this purpose, the whole set of codes have been applied to the LHD NBIs in a joint activity between Consorzio RFX and NIFS, with the goal of comparing and benchmarking the codes with the experimental data. A description of these modeling activities and a discussion of the main results obtained are reported in this paper.
- OSTI ID:
- 21611699
- Journal Information:
- AIP Conference Proceedings, Journal Name: AIP Conference Proceedings Journal Issue: 1 Vol. 1390; ISSN 0094-243X; ISSN APCPCS
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
43 PARTICLE ACCELERATORS
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
ACCELERATORS
ANIONS
BEAM INJECTION
BEAM INJECTION HEATING
CHARGED PARTICLES
CLOSED PLASMA DEVICES
COMPUTERIZED SIMULATION
DESIGN
ELECTROSTATIC ACCELERATORS
ENERGY RANGE
HEATING
ION SOURCES
IONS
ITER TOKAMAK
KEV RANGE
LHD DEVICE
MEV RANGE
NEUTRAL ATOM BEAM INJECTION
PERFORMANCE
PLASMA BEAM INJECTION
PLASMA HEATING
PLASMA SIMULATION
RF SYSTEMS
SIMULATION
TEST FACILITIES
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS
US NATIONAL IGNITION FACILITY
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
ACCELERATORS
ANIONS
BEAM INJECTION
BEAM INJECTION HEATING
CHARGED PARTICLES
CLOSED PLASMA DEVICES
COMPUTERIZED SIMULATION
DESIGN
ELECTROSTATIC ACCELERATORS
ENERGY RANGE
HEATING
ION SOURCES
IONS
ITER TOKAMAK
KEV RANGE
LHD DEVICE
MEV RANGE
NEUTRAL ATOM BEAM INJECTION
PERFORMANCE
PLASMA BEAM INJECTION
PLASMA HEATING
PLASMA SIMULATION
RF SYSTEMS
SIMULATION
TEST FACILITIES
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTORS
TOKAMAK DEVICES
TOKAMAK TYPE REACTORS
US NATIONAL IGNITION FACILITY