Conceptual design study for the ORMAK-F/BX facility
Conference
·
OSTI ID:4415739
From 5th symposium on engincering problems of fusion research; Princeton, New Jersey, USA (6 Nov 1973). Consideration is being given in the U S. to a large, injectionheated tokamak that could attain the zero-power Lawson criterion with H plasma in the late 1970's. The facility would be designed for subsequent replacement of some internal components and addition of shielding and containment to permit D-T burning experiments. An 8-manyear conceptual design study is to be accomplished in FY-1974 at Oak Ridge; this project is called ORMAK- F/BX for Oak Ridge Tokamak Feasibility and Burning Experiments. The F/BX reference design is now evolving. Conservative projections of plasma behavior indicate that the toroidal field coils must be about 5-meter bore diameter. Superconducting NbTi has been chosen for the TF coil windings and the plasma driving system will use an iron core and return yokes. (auth)
- Research Organization:
- Oak Ridge National Lab., Tenn. (USA)
- NSA Number:
- NSA-29-009209
- OSTI ID:
- 4415739
- Report Number(s):
- CONF-731114--12
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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