Abstract
SCOUT – a simple but self-consistent impurity model [1–4]– is used to describe impurity production and transport in the Frascati Tokamak Upgrade (FTU) operated with a molybdenum alloy (TZM) poloidal or segmented toroidal limiter. The values of main plasma impurity concentration parameter Z eff, radiated power fraction F P ≡ P rad/ P in, and edge plasma density and temperature are computed and compared with measurements. Good agreement between model and experiment is found for medium to high plasma densities while at the lowest density Z eff and F P are typically underestimated and overestimated respectively.
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