After several years of successful RFX-mod operations, both in RFP and Tokamak configurations, an upgrade of the machine has been conceived. In particular, the vacuum vessel might be removed with the aim of improving passive MHD control and enabling plasma rotation at higher currents. In this paper, a detailed analysis of the new magnetic front-end is presented, with particular emphasis on the computation of the magnetic field errors generated at the poloidal gaps during transient phases of the discharge. At this purpose, a non-linear MHD equilibrium code, MAXFEA, has been used to provide the input data for the 3D electromagnetic analyses in the time domain carried out with the CAFE code.
All Science Journal Classification (ASJC) codes
- Nuclear Energy and Engineering
- Materials Science(all)
- Civil and Structural Engineering
- Mechanical Engineering
Bettini, P., Finotti, C., Grando, L., Marchiori, G., & Specogna, R. (2017). Modeling of the magnetic field errors of RFX-mod upgrade. Fusion Engineering and Design, 123, 518 - 521. https://doi.org/10.1016/j.fusengdes.2017.06.001