Removal of Tritium from Gas Flows from Working Areas of Nuclear Facilities

被引:0
|
作者
Rozenkevich, M. B. [1 ]
Kulov, N. N. [2 ]
Pak, Yu. S. [1 ]
Bukin, A. N. [1 ]
Moseeva, V. S. [1 ]
Marunich, S. A. [1 ]
机构
[1] D Mendeleev Univ Chem Technol Russia, Moscow 125047, Russia
[2] Russian Acad Sci, Kurnakov Inst Gen & Inorgan Chem, Moscow 119991, Russia
关键词
tritium; gas flows; methods of removal; hydrogen; water; adsorption; phase isotope exchange; DETRITIATION SYSTEM; WATER; HYDROCARBONS; TECHNOLOGY; EFFICIENCY;
D O I
10.1134/S0040579523030156
中图分类号
TQ [化学工业];
学科分类号
0817 ;
摘要
Some methods were considered to remove tritium-containing hydrogen compounds from various gas flows from scientific and production facilities in the nuclear and thermonuclear power industry. The possibilities of tritium removal from a gas flow in the form of hydrogen were analyzed, and it was concluded that these methods can be applied at low flow rates of the gas being purified. At high gas flow rates, the main detritiation methods are adsorption and water phase isotope exchange. Both these methods include the preliminary catalytic oxidation of tritium-containing molecules to water with the further removal of tritiated water from the gas. The main technological parameters of these methods were compared, and it was inferred that phase isotope exchange has great advantages.
引用
收藏
页码:239 / 247
页数:9
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