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Formation and evolution of a wall protective plasma shield in a hard disruption

A. Sestero1995年被引用 5Nuclear FusionIF 3出版社

The behaviour of the material ablated from the wall in a hard disruption is analysed, in order mainly to ascertain its capability of protecting the wall from more severe damage. The investigation is limited to the fast first phase of the disruption, during which most of the bulk plasma thermal energy is given off. Within the ablated material an interaction region and a transmission region are defined. The first region (the 'virtual limiter') is where the bulk plasma thermal energy is dumped and the associated kinetic energy flux changed to radiation flux. The second region (the 'plasma shield') is where the radiative energy flux is attenuated through interaction with ablation matter, thus preventing more serious injuries to the wall. The whole problem is investigated in terms of a simplified mathematical model, which is shown to have a similarity solution. By making further approximations, an explicit solution is derived in full analytical terms. Applications are made to ITER type and IGNITOR type tokamaks

日本語訳

硬破裂における壁から剥離した材料の挙動を解析し、主として、より深刻な損傷から壁を保護する能力を評価することを目的とする。調査は、バルクプラズマの熱エネルギーの大部分が放出される破裂の高速初期段階に限定される。剥離した材料内には、相互作用領域と伝達領域が定義される。第一の領域(「仮想リミター」)は、バルクプラズマの熱エネルギーが堆積し、それに伴う運動エネルギーフラックスが放射フラックスに変換される場所である。第二の領域(「プラズマシールド」)は、放射エネルギーフラックスが剥離物質との相互作用を通じて減衰し、それにより壁へのより深刻な損傷が防止される場所である。この問題全体は、簡略化された数学的モデルに基づいて調査され、このモデルが相似解を有することが示される。さらに近似を進めることにより、完全な解析的表現による明示的な解が導出される。適用は、ITER型およびIGNITOR型トカマクに対して行われる。

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iter中精度(概要文一致)

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Plasma disruption
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