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
复制
发表时间:
2000
影响因子:
3.1
通讯作者:
A. Peacock
A. Peacock
中科院分区:
工程技术2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

文献摘要

被引文献

相似文献

采用全燃烧、热重分析和热脱附等方法研究了D-D等离子体辐照的TFTR石墨瓦和第一批氚辐照的JET石墨瓦上的氚分布。燃烧测量表明,>98.9%的氚被捕获在厚度小于50 μm的层中,其余的则散布在整个瓷砖中。氚在瓷砖表面的分布是不均匀的。很大一部分存在于瓦片之间的间隙中。在含0.1%氢气的氦气流中,加热至1100°C的JET瓦暴露于等离子体一侧的石墨盘在10850 °C时显示出最高的氚释放速率。完全燃烧和热释放的氚测量之间的协议是相当不错的。在约400°C的湿空气流下,石墨瓦上的氚被释放至>95%。大部分氚可以用胶带从瓷砖表面去除。
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.