量研学術機関リポジトリ「QST-Repository」は、国立研究開発法人 量子科学技術研究開発機構に所属する職員等が生み出した学術成果（学会誌発表論文、学会発表、研究開発報告書、特許等）を集積しインターネット上で広く公開するサービスです。 Welcome to QST-Repository where we accumulates and discloses the academic research results(Journal Publications, Conference presentation, Research and Development Report, Patent, etc.) of the members of National Institutes for Quantum Science and Technology.
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Power handling in the main plasma and divertor has been investigated in steady-state Japan Demo concept of 1.5 GW-level fusion power and the major radiaus of Rp = 8.5m. System code (TPC) survey for the Ar impurity seeding suggested the designed <ne> of 6.6-7.2x1019m-3 was lower than that in ITER. The divertor plasma simulation (SONIC) was performed in the divertor leg length of 1.6 m with the fixed exhaust power to the edge of Pout = 250MW and the total radiation fraction of frad = Prad/Pout = 0.8, as the first step to investigate appropriate design of the divertor size and geometry. Appropriate fuel and Ar puff rates were determined, where Praddiv was ~150MW (fraddiv ~ 0.6), (nAr/ne)SOL was decreased to 0.4-0.45% and nemid was increased to 2.3-2.4x1019m-3. In the outer divertor, the significant radiation peak was maintained in the divertor leg (near the separatrix) at 0.9-1.2 m below the X-point. At the outer target, partial detachment was produced near the strike-point (rdiv < 15 cm), and the peak qtarget at the attached region was ~5 MWm-2. At the inner divertor target, full detachment of ion flux was not produced due to Tediv = Tidiv ~1eV, and the peak qtarget was also ~5 MWm-2 mostly due to the surface-recombination. These results suggest a power exhaust scenario in Demo and the divertor design concept with long leg length, in which the peak-qtarget can be reduced less than 10 MWm-2 for both inner and outer divertor.
会議概要（会議名, 開催地, 会期, 主催者等）
22nd International Conference on Plasma Surface Interactions in Controlled Fusion Devices
Simulation Studies of the Divertor Geometry and Plasma Parameters for 1.5 GW Fusion Power Demo Reactor
