RF test blanket sub-module with ceramic breeder and helium cooling for test in ITER

被引:0
|
作者
Kovalenko, V
Kapyshev, V
Leshukov, A
Poliksha, V
Shatalov, G
Strebkov, Y
Strizhov, A
Sviridenko, M
机构
[1] NA Dollezhal Res & Dev Inst Power Engn, Moscow 101000, Russia
[2] Russian Res Ctr, Kurchatov Inst, Moscow 123182, Russia
关键词
fusion; blanket; test blanket sub-module; helium; ceramic;
D O I
10.1016/j.fusengdes.2005.09.019
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
International thermonuclear experimental reactor (ITER) is anticipated as the only one step to DEMO fusion reactor. One of its main objectives is to demonstrate the availability and integration of technologies essential for a fusion reactor by testing of components for a future reactor including the test blanket modules (TBM) with different types of breeding materials. RF proposed to divide the TBM on two parts and to use two independent test blanket sub-modules (TBSM) which fixed on the frame in ITER horizontal experimental port for testing. CHC TBSM design description, its mechanical attachment on the frame, and principle schemes of helium cooling system and tritium cycle system are presented in this paper. (c) 2005 Elsevier B.V. All rights reserved.
引用
收藏
页码:199 / 203
页数:5
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