FusionPapers
図版検索トレンドwiki日本の研究
© 2026 FUSIONPAPERS
About法務情報
トップに戻る

Impurity transport studies by means of tracer-encapsulated solid pellet injection in neutral beam heated plasmas on LHD

N Tamura, S Sudo, K V Khlopenkov, S Kato, V Yu Sergeev, S Muto, K Sato, H Funaba, K Tanaka, T Tokuzawa2003年Plasma Physics and Controlled FusionIF 2.2出版社

The quantitative properties of impurity transport in large helical device (LHD) plasmas heated by neutral beam injection have been investigated by means of tracer-encapsulated solid pellet (TESPEL) injection. In the case of a titanium (Ti) tracer, the behaviour of the emission lines from the highly ionized Ti impurity, Ti Kα(EHe−like∼4.7 keV) and Ti XIX (λ = 16.959 nm), has been observed clearly by a soft x-ray pulse height analyzer and a vacuum ultraviolet spectrometer, respectively. A fairly longer decay time of the Ti Kα emission lines is obtained above the value of a line-averaged electron density, 3.0×1019 m−3. The dependence of the behaviour of the Ti tracer impurity on the line-averaged electron density below the value of that, 3.5×1019 m−3 is in qualitative agreement with the characteristics obtained from the observation of the behaviour of an intrinsic metallic impurity in neutral beam heated plasmas on LHD. In order to estimate the properties of the Ti impurity transport quantitatively, the one-dimensional impurity transport code, MIST has been used. As a result of the transport analysis with the MIST code, even an small inward convection should be necessary to account for the experimental results with the value of the line-averaged electron density, 3.5×1019 m−3. In order to examine the experimentally obtained transport coefficients, neoclassical analysis with respect to the radial impurity flux has been performed. The inferred rise of the inward convection cannot be explained solely by neoclassical impurity transport. Therefore, in order to account for the inward convection, the effect of a radial electric field and/or some other effect must be taken into account additionally.

日本語訳

大型ヘリカル装置(LHD)プラズマにおける不純物輸送の定量的特性は、トレーサー封入固体ペレット(TESPEL)注入により調査された。チタン(Ti)トレーサーの場合、高電離Ti不純物からの輝線、すなわちTi Kα(E∼4.7 keV)およびTi XIX(λ = 16.959 nm)の挙動が、それぞれ軟X線パルス波高分析器および真空紫外分光器により明確に観測された。Ti Kα輝線の減衰時間は、線平均電子密度が3.0×10¹⁹ m⁻³を超えるとかなり長くなることが得られた。線平均電子密度が3.5×10¹⁹ m⁻³未満の値におけるTiトレーサー不純物の挙動の依存性は、中性粒子ビーム加熱プラズマにおける内在性金属不純物の挙動の観測から得られた特性と定性的に一致する。Ti不純物輸送の特性を定量的に評価するため、一次元不純物輸送コードであるMISTが使用された。MISTコードによる輸送解析の結果、線平均電子密度が3.5×10¹⁹ m⁻³の値における実験結果を説明するには、わずかな内向き対流が必要であることが示された。実験的に得られた輸送係数を検証するため、動径方向の不純物フラックスに関する新古典解析が実施された。推定された内向き対流の増大は、新古典的不純物輸送のみでは説明できない。したがって、この内向き対流を説明するためには、動径電場の効果および/またはその他の効果を追加的に考慮する必要がある。

装置

lhd高精度(タイトル一致)

wiki

ImpurityNeutral beamNeutral beam injectionLHDPellet injectionImpurity transport
この論文にはまだAI要約がありません。

関連論文

Impurity transport in the wendelstein VII-A stellarator

1985Nuclear Fusion

Mitigation of the tracer impurity accumulation by EC heating in the LHD

2016Plasma Physics and Controlled Fusion

Observation of neoclassical impurity transport in Ohmically heated plasmas of CDX-U low aspect ratio tokamak

2002Plasma Physics and Controlled Fusion

Impurity transport in ohmically heated TFTR plasmas

1989Nuclear Fusion

Observation of impurity accumulation and its compatibility with high plasma performance in W7-X

2023Plasma Physics and Controlled Fusion

Impurity transport driven by kinetic ballooning mode in the strong gradient pedestal of tokamak plasmas

2025Nuclear Fusion

Charge dependence of neoclassical and turbulent transport of light impurities on MAST

2015Plasma Physics and Controlled Fusion

A review of impurity transport characteristics in the LHD

2016Plasma Physics and Controlled Fusion

New particle transport diagnostics with tracer-encapsulated solid pellet

2001Plasma Physics and Controlled Fusion

Effects of temperature gradient driven turbulence and core MHD instability on particle transport in HL-2A L-mode plasmas

2020Nuclear Fusion