ABSTRACT The tritium exhaust behavior from the Large Helical Device (LHD) was observed in the first deuterium plasma experimental campaign. Tritium in the exhaust gas was monitored at the conducted by use of the ionization chamber and water bubbler system with the discrimination of chemical forms. The observation results indicated that (i) tritium on the surface of the first wall and divertor tiles as plasma facing components was released by the hydrogen isotope exchange reaction of the glow discharge cleaning operation and the diffusion-limited process was suggested in the tritium release behavior from the bulk, (ii) the amount of tritium release from the LHD vacuum vessel was about one-third of the produced tritium and the mostly produced tritium was still retained at the end of plasma experimental campaign, (iii) the ratio of exhausted tritium from the LHD vacuum vessel was larger than that in the case of JT-60U based on the carbon materials as the plasma-facing components. It indicated that the tritium inventory would be reduced and controlled by the kind of plasma-facing materials.

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第一次氘等离子体实验中大型螺旋装置氚的排气行为

摘要 在第一次氘等离子体实验活动中观察到大型螺旋装置 (LHD) 的氚排放行为。使用电离室和水起泡器系统对废气中的氚进行监测，并区分化学形式。观察结果表明，(i) 第一壁和偏滤器瓦表面上的氚作为面向等离子体的组件通过辉光放电清洁操作的氢同位素交换反应释放，并且氚释放行为表明扩散限制过程从整体来看，(ii) LHD 真空容器释放的氚量约为产生的氚的三分之一，并且大部分产生的氚在等离子体实验活动结束时仍然保留，(iii) 从 LHD 真空容器中排出的氚的比率大于基于碳材料作为面向等离子体组件的 JT-60U 的情况。它表明氚库存将通过面向等离子体的材料种类减少和控制。