Tritium recovery from tritiated water by electrolysis

被引:9
作者
Bellanger, G [1 ]
Rameau, JJ
机构
[1] Ctr Etud Valduc, Commissariat Energie Atom, F-21120 Is Sur Tille, France
[2] Ecole Natl Super Electrochim & Electromet, Inst Natl Polytech Grenoble, F-38402 St Martin Dheres, France
来源
FUSION TECHNOLOGY | 1999年 / 36卷 / 03期
关键词
tritium; tritiated water; diffusion;
D O I
10.13182/FST99-A110
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
In addition to the tritiated water produced by the Commissariat a l'Energie Atomique, large quantities result from the development of controlled fusion reactors for power generation (International Thermonuclear Experimental Reactor). To obtain a new industrial method of reducing tritiated water, an electrolytic rather than a chemical process was developed A prototype electrolyzer is described and the results obtained are given. In this process, the tritium recovery system is based on the principle of a gas diffusion Pd-Ag electrode incorporating a tritium charging cathode, which produces very pure hydrogen isotope gases. This is for converting (H2O)-H-3 to high-purity H-3(2) and its isotopes from tritiated water with >30 TBq/cm(3) radioactivity (>50% (H2O)-H-3), The prototype module has been tested in a hot laboratory. The overall operating time exceeded 1500 h, and 6 g of gaseous tritium were produced without difficulty.
引用
收藏
页码:296 / 308
页数:13
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