Tritium detection in plasma facing component by imaging plate technique

Tritium detection in plasma facing component by imaging plate technique
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通过成像板技术检测等离子体组件中的氚

DOI:
10.1016/s0022-3115(00)00513-4
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发表时间:
2001
影响因子:
3.1
通讯作者:
T. Saze
T. Saze
中科院分区:
工程技术2区
文献类型:
--
作者:
K. Miyasaka;T. Tanabe;G. Mank;K. Finken;V. Philipps;D. Walsh;K. Nishizawa;T. Saze

文献摘要

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氚成像板技术(TIPT)已成功地应用于测量TEXTOR中用作限制器的各种石墨板上的氚面分布。观察到氚在ALT-II瓦上的分布非常均匀,与氘的分布不同,再沉积层中的氚相当少。这种氚在TEXTOR中石墨瓦上的分布与那些在JET和TFTR中使用氚作为燃料气体或NBI注入的那些不同。在喷气发动机和TFTR中,氚是燃料的一部分,并以与氘类似的方式共同沉积和保留。在像TEXTOR这样的设备中,高能triton与热化的氘核解耦,并显示出不同的保留行为;主要的保留机制是深注入,而不是与再沉积为主的区域上的侵蚀碳共沉积。还发现,氚分布测量等离子体壁相互作用提供了有用的新信息。
Tritium imaging plate technique (TIPT) has been successfully applied to measure the tritium areal distribution on various graphite tiles used as limiters in TEXTOR. It is observed that tritium distribution on the ALT-II tile is quite homogeneous and different from deuterium distribution and the tritium in redeposited layer is rather small. Such tritium distribution on the graphite tiles in TEXTOR behaves different compared to those in JET and TFTR where tritium was used as fueling gas or NBI injection. In JET and TFTR the tritium is part of the fuel and is co-deposited and retained in a similar manner as the deuterium. In a device like TEXTOR, the high-energy tritons are decoupled from the thermalized deuterons and show different behavior of retention; the main retention mechanism is deep implantation rather than co-deposition with eroded carbon on redeposition-dominated areas. It is also found that the tritium distribution measurements give useful new information on plasma-wall interactions.