Configuration review of TFCX design options
Conference
·
OSTI ID:5437905
As part of the preconceptual design effort of the Tokamak Fusion Core Experiment (TFCX), several candidate design options have been explored in order to identify a preferred option that will be developed in further detail during the conceptual design phase of the TFCX program. The development of the TFCX concepts has been a collaborative effort between the Princeton Plasma Physics Laboratory (PPPL) and the Fusion Engineering Design Center (FEDC) with broad community input. The design options being considered include an all-superconducting design, a superconducting/copper toroidal field (TF) hybrid design, and several different all-copper configurations.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5437905
- Report Number(s):
- CONF-840614-106; ON: DE85016381
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700200* -- Fusion Energy-- Fusion Power Plant Technology
DESIGN
DOCUMENT TYPES
ELECTRIC COILS
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
EQUIPMENT
HYBRID SYSTEMS
MAGNET COILS
MAGNETS
REVIEWS
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
TFCX REACTORS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
700200* -- Fusion Energy-- Fusion Power Plant Technology
DESIGN
DOCUMENT TYPES
ELECTRIC COILS
ELECTRICAL EQUIPMENT
ELECTROMAGNETS
EQUIPMENT
HYBRID SYSTEMS
MAGNET COILS
MAGNETS
REVIEWS
SUPERCONDUCTING DEVICES
SUPERCONDUCTING MAGNETS
TFCX REACTORS
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS