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翻訳と辞書　辞書検索 [ 開発暫定版 ] スポンサード リンク Lithium Tokamak Experiment ： ウィキペディア英語版 Lithium Tokamak Experiment The Lithium Tokamak Experiment (LTX), and its predecessor, the Current Drive Experiment-Upgrade (CDX-U), are devices dedicated to the study of liquid lithium as a plasma-facing component (PFC). One of the attractive features of a liquid lithium PFC is that it virtually eliminates recycling, or the re-introduction of cold gas back into the plasma from the vacuum chamber walls. This is because lithium has a high chemical reactivity with atomic hydrogen, which is then retained in the PFC. Flowing liquid lithium can also potentially handle the high power densities expected on fusion reactor walls. In addition, lithium has a low atomic number, Z. This gives the lowest possible energy loss by radiation from PFC material that may end up in the plasma, because radiation increases strongly with increasing Z. ==Tokamak performance== All major tokamaks have obtained their best performance under low recycling conditions. If a fully non-recycling wall can be achieved, theory predicts that the basic nature of magnetic confinement will be changed. The temperature and density profiles, and plasma current distributions, would potentially eliminate deleterious plasma instabilities. Furthermore, the transport mechanisms causing the loss of energy and particles would be reduced, and plasmas with higher energy confinement could result. 抄文引用元・出典: フリー百科事典『 ウィキペディア（Wikipedia）』 ■ウィキペディアで「Lithium Tokamak Experiment」の詳細全文を読む スポンサード リンク 翻訳と辞書 : 翻訳のためのインターネットリソース Copyright(C) kotoba.ne.jp 1997-2016. All Rights Reserved.