Numerical Analysis of Divertor Plasma for Demo‐CREST

Ishida, M.; Maeki, K.; Hiwatari, Ryoji; Bonnin, X.; Zhu, Shengyu; Hatayama, A.; Schneider, R.; Coster, D.

doi:10.1002/ctpp.201010059

Cited by 2 publications

(1 citation statement)

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“…In a highly radiative plasma, the radiation power distribution in the divertor significantly affects the plasma detachment and the target heat load profile [13]. Recently, the divertor performance of Demo reactors such as Demo-CREST [15] and ITER CDA-size Demo [16,17] has been evaluated using an integrated SOLPS code package, where multi-charged seeding neon (Ne) transport is treated by fluid approximation. The former study fixed the exhausted power and particle fluxes from the confined plasma to the scrapeoff layer (SOL) and divertor, while the latter study coupled core-pedestal modelling (1.5D ASTRA) and SOL-divertor modelling (scaling low from the SOLPS evaluations).…”

Section: Introductionmentioning

confidence: 99%

A simulation study of large power handling in the divertor for a Demo reactor

et al. 2013

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Power exhaust for a 3 GW class fusion reactor with an ITER-sized plasma was investigated by enhancing the radiation loss from seeding impurity. The impurity transport and plasma detachment were simulated under the Demo divertor condition using an integrated divertor code SONIC, in which the impurity Monte-Carlo code, IMPMC, can handle most kinetic effects on the impurity ions in the original formula. The simulation results of impurity species from low Z (neon) to high Z (krypton) and divertor length with a plasma exhausted power of 500 MW and radiation loss of 460 MW, and a fixed core–edge boundary of 7 × 1019 m−3 were investigated at the first stage for the Demo divertor operation scenario and the geometry design. Results for the different seeding impurities showed that the total heat load, including the plasma transport and radiation , was reduced from 15–16 MW m−2 (Ne and Ar) to 11 MW m−2 for the higher Z (Kr), and extended over a wide area accompanied by increasing impurity recycling. The geometry effect of the long-leg divertor showed that full detachment was obtained, and the peak qtarget value was decreased to 12 MW m−2, where neutral heat load became comparable to and due to smaller flux expansion. Fuel dilution was reduced but was still at a high level. These results showed that a divertor design with a long leg with higher Z seeding such as Ar and Kr is not fulfilled, but will be appropriate to obtain the divertor scenario for the Demo divertor. Finally, influences of χ and D⊥ enhancement were seen significantly in the divertor, i.e. the radiation and density profiles became wider, leading to full detachment. Both qtarget near the separatrix and Te at the outer flux surfaces were decreased to a level for the conventional technology design. On the other hand, the problem of fuel dilution became worse. Extrapolation of the plasma transport coefficients to ITER and Demo, where density and temperature will be higher than ITER and edge-localized modes are mitigated, is a key issue for the divertor design.

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