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

Simulation of main chamber wall temperature rise resulting from massive neon gas injection shutdown of ITER

E.M. Hollmann, D.A. Humphreys, P.B. Parks2012年Nuclear FusionIF 3出版社

Simulations were performed to estimate the main chamber wall heating in ITER resulting from rapid discharge shutdown by neon massive gas injection (MGI). The TokSys current diffusion model coupled with a simplified impurity transport model was used. Impurity parallel flow was treated with a single-fluid pressure-driven flow model. Impurity cross-field diffusion was treated with an empirical diffusion coefficient estimated from present experiments, while impurity poloidal rotation was included empirically by extrapolation in minor radius from present experiments to ITER. For single-valve neon MGI, maximum wall temperatures of order 1100 K are predicted, somewhat below the melting temperature of beryllium (1560 K). Lower temperature excursions were obtained by increasing the number of gas valves, while higher wall temperatures could be obtained by turning up initial plasma thermal energy or cross-field transport coefficients. Highest wall temperatures tended to occur on the centre post during the start of the current quench phase, consistent with present experiments. These results suggest that a single port may be sufficient for safely initiating rapid shutdown in ITER, leaving other ports free for subsequent rapid shutdown tasks such as runaway electron mitigation.

日本語訳

ITERにおける急速停止のためのネオン大量ガス注入(MGI)による主容器壁の加熱を評価するため、シミュレーションを実施した。簡略化された不純物輸送モデルを結合したTokami電流拡散モデルを用いた。不純物の平行流は、単流体の圧力駆動流モデルで扱った。不純物の横断方向拡散は、現在の実験から推定した経験的拡散係数を用いて扱い、一方、不純物のポロイダル回転は、現在の実験からITERへの小半径方向の外挿により経験的に含めた。単一バルブによるネオンMGIの場合、最大壁温度は約1100 Kと予測され、ベリリウムの融点(1560 K)をやや下回る結果となった。ガス注入バルブの数を増やすことで、より低い温度上昇が得られ、一方、初期プラズマ熱エネルギーまたは横断方向輸送係数を増加させることで、より高い壁温度が得られる可能性がある。最高壁温度は、電流クエンチ開始時にセンターポストで発生する傾向があり、これは現在の実験と一致する。これらの結果は、ITERにおける急速停止を安全に開始するには単一のポートで十分であり、他のポートを runaway 電子緩和などのその後の急速停止タスクのために空けておくことができることを示唆している。

装置

iter高精度(タイトル一致)

wiki

ITER
この論文にはまだAI要約がありません。

関連論文

Evaluation of SS316 first wall material for activation and afterheat for maintenance purposes

1991Fusion Engineering and Design

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

2023Plasma Physics and Controlled Fusion

Impurity transport in ohmically heated TFTR plasmas

1989Nuclear Fusion

Active particle control experiments and critical particle flux discriminating between the wall pumping and fuelling in the compact plasma wall interaction device CPD spherical tokamak

2009Nuclear Fusion

Effect of fuel isotope mass on q-profile formation in JET hybrid plasmas

2020Nuclear Fusion

Analysis of metallic impurity content by means of VUV and SXR diagnostics in hybrid discharges with hot-spots on the JET-ITER-like wall poloidal limiter

2019Plasma 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

Impact of the temperature ratio on turbulent impurity transport in Wendelstein 7-X

2020Nuclear Fusion

Short term dynamics of the reaction between beryllium and steam on the PFCs coating of ITER

1996Fusion Engineering and Design

Characterization and controllability of radiated power via extrinsic impurity seeding in strongly negative triangularity plasmas in DIII-D

2025Plasma Physics and Controlled Fusion