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Energy confinement of beam-heated divertor and limiter discharges in Doublet III

M. Nagami, M. Kasai, A. Kitsunezaki, T. Kobayashi, S. Konoshima, T. Matsuda, N. Miya, H. Ninomiya, S. Sengoku, M. Shimada1984年被引用 71Nuclear FusionIF 3出版社

Observation of the intensity of the recycling particle flux at the main plasma edge for various limiter and divertor discharges indicates that the gross energy confinement of beam-heated discharges is closely related to the intensity of the edge particle flux. In limiter discharges, the global particle confinement time and the energy confinement time τE show many similarities: 1) linear Ip dependence at Ip < 600 kA, 2) no BT dependence, and 3) deterioration against injection power. Improvement of τE by increasing Ip, for example, is associated with high temperatures at the plasma edge region accompanied by reduced particle recycling. – Divertor discharges with low particle recycling around the main plasma show better energy confinement than limiter discharges at high plasma densities. The improvement of τE is primarily originated in the reduction of heat transport at the main plasma edge region, which is associated with the reduction of recycling particle flux at the main plasma edge. Under certain operation condition, for example, excessive cold-gas puffing, the discharge shows relatively high scrape-off plasma density and strong particle recycling between the main plasma and the limiter. The energy confinement time of these discharges degrades somewhat or reduces completely to that of the limiter discharge. – In low-recycling divertor discharges, the central electron and ion temperature is proportional to the injection power, and the plasma stored energy is proportional to ePabs (scales as INTOR scaling). With ≈ 4 MW beam injection, high-temperature and high-density plasmas were obtained (stored energy up to 280 kJ, Te(0) ≈ Ti(0) ≈ 2.5–3.0 keV at e ≈ (6–7) × 1013 cm−3, τE* ≈ 70 ms).

日本語訳

種々のリミター及びダイバータ放電における主プラズマ周辺部でのリサイクリング粒子束の強度の観測は、ビーム加熱放電のグロスエネルギー閉じ込めが周辺粒子束の強度と密接に関連していることを示している。リミター放電では、全体粒子閉じ込め時間とエネルギー閉じ込め時間τEは多くの類似点を示す:1) Ip < 600 kAでの線形のIp依存性、2) BT依存性がないこと、3) 入射パワーに対する劣化。例えば、Ipの増加によるτEの改善は、粒子リサイクリングの低減を伴うプラズマ周辺領域での高温と関連している。– 主プラズマ周辺での粒子リサイクリングが低いダイバータ放電は、高プラズマ密度においてリミター放電よりも良好なエネルギー閉じ込めを示す。τEの改善は、主に主プラズマ周辺領域での熱輸送の低減に起因しており、これは主プラズマ周辺でのリサイクリング粒子束の低減と関連している。特定の運転条件、例えば過剰な冷ガスパフ入射では、放電は比較的高いスクレイプオフプラズマ密度と、主プラズマとリミター間の強い粒子リサイクリングを示す。これらの放電のエネルギー閉じ込め時間は、いくぶん劣化するか、あるいは完全にリミター放電の値まで低下する。– 低リサイクリングダイバータ放電において、中心電子・イオン温度は入射パワーに比例し、プラズマ蓄積エネルギーはePabsに比例する(INTORスケーリング則に従う)。≈ 4 MWのビーム入射により、高温・高密度プラズマが得られた(蓄積エネルギーは最大280 kJ、e ≈ (6–7) × 1013 cm−3 で Te(0) ≈ Ti(0) ≈ 2.5–3.0 keV、τE* ≈ 70 ms)。

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DivertorLimiterEnergy confinementDoublet III
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