The water detritiation system of the ITER tritium plant

被引：47
|
作者：
Iwai, Y [1 ]
Misaki, Y
Hayashi, T
Yamanishi, T
Konishi, S
Nishi, M
Ninomiya, R
Yanagimachi, S
Senrui, S
Yoshida, H
机构：
[1] Japan Atom Energy Res Inst, Tritium Engn Lab, Tokai, Ibaraki 3191195, Japan
[2] Showa Engn Co LTD, Minato Ku, Tokyo 1080023, Japan
[3] ITER JCT, Naka, Ibaraki 3110102, Japan
来源：
FUSION SCIENCE AND TECHNOLOGY | 2002年 / 41卷 / 03期
关键词：
D O I：
10.13182/FST02-A22759
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：
The water detritiation system (WDS) of tritium plant for the International Thermonuclear Experimental Reactor (ITER) was designed. The concept of the Combined Electrolysis Catalytic Exchange (CECE) process was selected for the WDS. The design conditions are (a) tritium concentration of waste water: 3.7x10(10)similar to3.7x10(11) Bq/kg, (b) waste water flow rate: 20 kg/h (1100 mol/h), a net working rate: 300 days, annual capacity: 150 tons/year (c) tritium concentration in the H-2 discharged to environment: 6.5x10(1) Bq/m(3), (d) tritium concentration in the H2O vapor discharged to environment: 3.7x10(3) Bq/m(3), (e) tritium concentration in the electrolyzer: similar to1.85x10(13) Bq/kg. Tritium concentration in the electrolyzer is determined considering the lifetime of the electrolyzer which depends on tritium concentration. Design value of height of a unit (30cm) of water-hydrogen isotopic exchange column and the correlation between the column internal flow rates and the column diameter were determined based on similar system for Japanese advanced thermal reactor (Fugen) moderated with heavy water.
引用
收藏
页码：1126 / 1130
页数：5
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