The externally applied loop voltage, required to drive current carrying magnetic configurations, such as tokamaks or reversed field pinches (RFP), can induce currents between the plasma and the surrounding conducting components, such as limiters, divertor sections, stabilizing plates or enclosing stabilizing shells with insulated electrical gaps. An appropriate modeling of this problem can quantify these currents and give constraints for the design of new devices. In this paper a methodology based on lumped element circuit is used to evaluate this problem for the case of in vessel components of the RFX-mod2, which led to a redesign of the electrical connections of plasma facing components. In the new design some parts, having applied potential in the kV range, are still exposed to the weakly ionized scrape off plasma. The process of arc formation between them and their prevention had been experimentally investigated and possible arc suppression strategies identified.
All Science Journal Classification (ASJC) codes
- Civil and Structural Engineering
- Nuclear Energy and Engineering
- Materials Science(all)
- Mechanical Engineering
Cavazzana, R., Marsango, L., Peruzzo, S., Zuin, M., Gnesotto, F., Marrelli, L., Spolaore, M., & Martines, E. (Accepted/In press). Design constraints on new vacuum components of RFX-mod2 upgrade using electrical modeling of reversed field pinch plasma. Fusion Engineering and Design, -. https://doi.org/10.1016/j.fusengdes.2018.04.103