Toroidal field coil design concept and structural support system for CTHR
The CTHR conceptual design consists of a magnetically confined (tokamak) fusion reactor fitted with a fertile uranium blanket. The fusion driver concept was based on an ignited plasma. All concepts and parameters were selected on the basis that technical feasibility would be achieved by 1995 to assure a viable commercial operation in the early to mid-21st century. The reactor was designed to achieve good fissile fuel production, with electricity production being a second order priority. However, the resulting concepts that evolved were all excellent power producers which significantly improved the economic performance. The subsystems discussed in the following paragraphs provide a background of the application for the TF coil design described in this report.
- Research Organization:
- Westinghouse Electric Corp., Pittsburgh, PA (USA). Fusion Power Systems Dept.
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC02-77ET52043
- OSTI ID:
- 6754597
- Report Number(s):
- WFPS-TME-80-009
- Country of Publication:
- United States
- Language:
- English
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