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Assessment of power deposition on plasma facing components inside WEST tokamak [Elektronski vir]
Brank, Matic ...
Assessment of plasma power deposition with the use of magnetic field-line tracing on tokamak plasma facing components is important in order to provide thermal loading of critical components in the ...fusion reactors. Such analysis can provide insight into PFC design and can improve the durability and safety of nuclear fusion reactors. This article describes a benchmark performed between two magnetic field-line tracing (FLT) codes, PFCFLUX [1] and SMITER [2]. The code PFCFLUX (Plasma Facing Components Flux) has been developed for heat flux calculations on those components, including shadowing effects. SMITER is a graphical user interface (GUI) framework, built around SMARDDA [3] kernel for magnetic field-line tracing and power deposition mapping on tokamak plasma-facing components (PFC) in the full 3-D CAD geometry of the machine. The main purpose of the benchmark presented here is the evaluation of the power deposition on the poloidal limiters (high and low field sides) and the divertor targets of WEST tokamak. Magnetic coils of WEST have been added to confine the originally circular plasma into and ITER-like ”D”-shape. As one of the main testing tokamaks for ITER, it is thus also suitable to provide assessment of heat loads on plasma facing components inside WEST. The input parameters to field-line tracing codes are the target geometry, shadowing geometry and 2-D equilibrium data. Target geometry describes the geometry where the power fluxes will be assessed. Field-lines are traced back from the target triangles into the scrape-off layer region. Shadowing geometry acts as a shadow. If field-lines of a target triangle hit the shadowing geometry, then this triangle is considered non-wetted. If the field-line does not hit anything after a user-defined maximum distance, then the target triangle is considered wetted, and power deposition can be calculated based on the provided heat flux profile. Equilibrium data contains information about magnetic field fluxes defined in R-Z space and are assumed to be axisymmetric in the toroidal direction.
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