Can wall and limiter erosion be eliminated in fusion reactors
Conference
·
OSTI ID:6360900
A pump limiter system is described which is compatible with in-situ recoating of the limiter surface. The recoating could be done during normal tokamak operation. We have shown how this system is compatible with most of the constraints of fusion reactor operation and might provide a significant advantage over magnetic diverter and some other pump limiter geometries.
- Research Organization:
- Argonne National Lab., IL (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6360900
- Report Number(s):
- CONF-811040-196; ON: DE83007695
- Country of Publication:
- United States
- Language:
- English
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