This work explores detailed power handling solutions for a class of high-field, highly-radiative negative triangularity (NT) reactors based around the MANTA concept (Rutherford et al 2024 Plasma Phys. Control. Fusion). The divertor design is kept as simple as possible, opting for a standard divertor with standard leg length. FreeGS is used to create an equilibrium for the boundary region, prioritizing a short outer leg length of only ∼50 cm (∼40% of the minor radius). The UEDGE code package is used for the boundary plasma solution to track plasma temperatures and fluxes to the divertor targets. It is found that for = 25 MW and m−3, conditions consistent with initial core transport modeling, little additional power mitigation is necessary. For a fixed impurity fraction of just 0.13% Ne in the plasma, the peak heat flux density at the more heavily loaded outer targets falls to 7.8 MW m−2, while the electron temperature remains just under 5 eV. Scans around the parameter space reveal that even at densities lower than in the primary operating scenario, can be increased up to 50 MW, so long as a slightly higher fraction of extrinsic radiator is used. With less than 1% neon (Ne) impurity content, the divertor still experiences less than 10 MW m−2 at the outer target. Design of the plasma-facing components includes a close-fitting vacuum vessel with a tungsten inner surface as well as FLiBe-carrying cooling channels fashioned into the VV wall directly behind the divertor targets. For the seeded heat flux profile, Ansys Fluent heat transfer simulations estimate that the outer target temperature remains at just below 1550 ∘C. Initial scoping of advanced divertor designs shows that for an X-divertor, detachment of the outer target becomes much simpler, and plasma fluxes to the targets drop considerably with only 0.01% Ne content.
本研究は、MANTA概念(Rutherford ら 2024 Plasma Phys. Control. Fusion)に基づく、高磁場・高放射の負三角形度(NT)炉のクラスに対する詳細な電力処理解決策を探るものである。ダイバータ設計は可能な限り単純に保ち、標準的なレッグ長を備えた標準ダイバータを選択している。FreeGSを用いて境界領域の平衡を生成し、外側レッグ長を僅か∼50 cm(小半径の∼40%)に短くすることを優先した。UEDGEコードパッケージを境界プラズマ解に使用し、ダイバータ標的へのプラズマ温度とフラックスを追跡する。 = 25 MW および m−3 の場合、初期のコア輸送モデリングと一致する条件では、追加の電力緩和はほとんど必要ないことが見いだされた。プラズマ中の不純物割合を僅か0.13% Neに固定すると、より大きな負荷を受ける外側標的におけるピーク熱流束密度は7.8 MW m−2に低下し、一方、電子温度