Can wall and limiter erosion be eliminated in fusion reactors
Conference
·
· Proc. Symp. Eng. Probl. Fusion Res.; (United States)
OSTI ID:6421287
Pump limiter designs, while generally simpler than magnetic diverters have two primarily problems: wall erosion and the resultant plasma impurity concentration. In principle, these problems can both be solved by artificially maintaining an impurity density of low-Z materials in the plasma edge region which should enable impurity deposition on the limiter and walls to exactly compensate erosion while at the same time producing negligible radiation loss from the plasma. In paper outlines a proposed method of in-situ maintenance of pump limiters for tokamak reactors, and describes how this system could be operated, perhap under steady-state conditions.
- Research Organization:
- Argonne Natl Lab, IL, USA
- OSTI ID:
- 6421287
- Report Number(s):
- CONF-811040-
- Journal Information:
- Proc. Symp. Eng. Probl. Fusion Res.; (United States), Journal Name: Proc. Symp. Eng. Probl. Fusion Res.; (United States); ISSN PSERD
- Country of Publication:
- United States
- Language:
- English
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