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Divertor heat flux mitigation in high-performance H-mode discharges in the National Spherical Torus Experiment

V.A. Soukhanovskii, R. Maingi, D.A. Gates, J.E. Menard, S.F. Paul, R. Raman, A.L. Roquemore, R.E. Bell, C.E. Bush, R. Kaita2009年被引用 39Nuclear FusionIF 3出版社

Experiments conducted in high-performance 1.0 and 1.2 MA 6 MW NBI-heated H-mode discharges with a high magnetic flux expansion radiative divertor in NSTX demonstrate that significant divertor peak heat flux reduction and access to detachment may be facilitated naturally in a highly shaped spherical torus (ST) configuration. Improved plasma performance with high βt = 15–25%, a high bootstrap current fraction fBS = 45–50%, longer plasma pulses and an H-mode regime with smaller ELMs has been achieved in the strongly shaped lower single null configuration with elongation κ = 2.2–2.4 and triangularity δ = 0.7–0.8. Divertor peak heat fluxes were reduced from 6–12 to 0.5–2 MW m−2 in ELMy H-mode discharges using the inherently high magnetic flux expansion fm = 15–25 and the partial detachment of the outer strike point at several D2 injection rates. A good core confinement and pedestal characteristics were maintained, while the core carbon concentration and the associated Zeff were reduced. The partially detached divertor regime was characterized by an increase in divertor radiated power, a reduction in ion flux to the plate and a large neutral compression ratio. Spectroscopic measurements indicated the formation of a high-density, low-temperature region adjacent to the outer strike point, where substantial increases in the volume recombination rate and C II, C III emission rates were measured.

日本語訳

高性能の1.0および1.2 MA、6 MWのNBI加熱Hモード放電において、高磁束増幅率を有する放射ダイバータを用いて実施された実験は、高閉じ込め性能を有する球状トーラス(ST)配位において、ダイバータ部のピーク熱流束の大幅な低減とダイバータのデタッチメントへの移行が自然に促進され得ることを実証している。βt = 15–25%の高いトロイダルベータ値、高いブートストラップ電流分率fBS = 45–50%、より長いプラズマパルス、より小さなELMを伴うHモード領域という改善されたプラズマ性能は、伸長度κ = 2.2–2.4、三角形度δ = 0.7–0.8を有する強く成形された下部シングルヌル配位において達成された。ダイバータ部のピーク熱流束は、本質的に高い磁束増幅率fm = 15–25と、いくつかのD2ガス入射速度における外側ストライク点の部分的デタッチメントを用いることにより、ELMy Hモード放電において6–12 MW m⁻²から0.5–2 MW m⁻²へ低減された。コアプラズマの閉じ込めとペデスタル特性は良好に維持され、一方でコアの炭素不純物濃度とそれに伴う実効電荷数Zeffは低減された。部分的にデタッチしたダイバータ領域は、ダイバータ放射パワーの増加、プレートへのイオン束の低減、および大きな中性粒子圧縮比を特徴としていた。分光測定により、外側ストライク点に隣接して高密度・低温領域が形成され、そこでは体積再結合率とC II、C III発光率の大幅な増加が測定された。

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DivertorH-modeNSTXSpherical torus
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