A mock-up of a tritium pellet injector for ITER

被引：2
|
作者：
Viniar, I
Saksaganskii, G
Skoblikov, S
Krasilnikov, I
Pimanikhin, S
机构：
[1] PELIN Lab Ltd, Moscow 125212, Russia
[2] DV Efremov Inst Electrophys Apparatus, St Petersburg 196641, Russia
[3] State Tech Univ, St Petersburg 195251, Russia
[4] All Russian Sci Res Inst Expt Phys, Sarov 607190, Russia
来源：
FUSION ENGINEERING AND DESIGN | 2001年 / 58-59卷
关键词：
pellet injector; ITER; tokamak; tritium;
D O I：
10.1016/S0920-3796(01)00360-X
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 ITER tokamak is to be equipped with a pellet injector for plasma fuelling. A tritium compatible pneumatic pellet injector with a screw extruder has been designed, tested with protium, and is under installation for testing at the experimental tritium loop in the Russian Nuclear Center in Sarov. The rectangular rod 3 x 4 mm(2) from condensed protium was extruded within 1500 s at rate of similar to 15 mm/s. Pellets similar to 3 mm in size formed from the rod were accelerated up to 500 m/s by helium under a pressure of 1 MPa with an :injection frequency of 1 and 2 Hz. The main injector subsystems and the current status of the work are described. (C) 2001 Elsevier Science B.V. All rights reserved.
引用
收藏
页码：313 / 317
页数：5
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