Gakushi Kawamura

1 Introduction For the operation of existing and future tokamak devices worldwide, managing divertor power exhaust remains a key challenge [1, 2]. Japan is currently working on the design activity of JA DEMO, which features a large major radius , minor radius and substantial fusion power [3, 4]. In an unmitigated plasma scenario of JA DEMO, the maximum steady-state power load on divertor targets significantly exceeds the engineering limit of .

1 Introduction One of the critical issues in the design of future fusion reactors is how to handle the high heat load on the divertor target. In particular, the spatial peak heat load on the target is an important criterion for evaluating its robustness. If the heat load distribution on the target can be assessed at a low computational cost, the number of scenarios requiring simulation by two-dimensional integrated codes such as SONIC [1, 2] or SOLPS-ITER [3, 4] can be significantly reduced.

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