Tritium profiles in tiles from the first wall of fusion machines and techniques for their detritiation
Tritium profiles in tiles from the first wall of fusion machines and techniques for their detritiation
复制标题
来自熔合机第一壁的瓷砖中的氚分布及其除氚技术
DOI:
10.1016/s0022-3115(00)00018-0
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发表时间:
2000
影响因子:
3.1
通讯作者:
A. Peacock
中科院分区:
文献类型:
--
作者:
R. Penzhorn;N. Bekris;W. Hellriegel;H. Noppel;W. Nägele;H. Ziegler;R. Rolli;H. Werle;A. Haigh;A. Peacock
Tritium profiles on a TFTR graphite tile exposed to D–D plasmas and a JET graphite tile from the first tritium campaigns were examined by full combustion, thermogravimetry and thermal desorption. Combustion measurements revealed that >98.9% of the tritium is trapped in a layer <50 μm thick, the remainder being spread throughout the tile. The tritium distribution on the tile surface is not homogeneous. A significant fraction resides in the gaps between tiles. Graphite disks from the plasma-exposed side of JET tiles heated up to 1100°C under a helium stream containing 0.1% hydrogen showed the highest tritium release rate at ∼850°C. The agreement between tritium measurements by full combustion and thermal release was reasonably good. Tritium on graphite tiles was released to >95% under a stream of moist air at about 400°C. A large fraction of tritium can be removed from the tile surface with adhesive tape.