Liquid lithium self-cooled breeding blanket design for ITER

被引:34
|
作者
Kirillov, IR [1 ]
Danilov, IV
Sidorenkov, SI
Strebkov, YS
Mattas, RF
Gohar, Y
Hua, TQ
Smith, DL
机构
[1] DV Efremov Sci Res Inst Electrophys Apparatus, STC Sintez, St Petersburg 189631, Russia
[2] Res & Dev Inst Power Engn, Moscow 101100, Russia
[3] Argonne Natl Lab, Fus Power Program, Chicago, IL 60439 USA
[4] Max Planck Inst Plasmaphys, ITER Garching Joint Work Site, D-85748 Garching, Germany
关键词
D O I
10.1016/S0920-3796(98)00199-9
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
To meet the technical objectives of the ITER extended performance phase (EPP) an advanced tritium breeding lithium/vanadium (Li/V) blanket was developed by two home teams (US and RF). The design is based on the use of liquid Li as coolant and breeder and vanadium alloy (V-Cr-Ti) as structural :material. The first wall is coated with a beryllium protection layer. Beryllium is also integrated in the blanket for neutron multiplication and improved shielding. The use of tungsten carbide in the primary shield and in vacuum vessel provides adequate protection for toroidal field coils. A self-healing electrical insulator in the form of CaO or AIN coating layer is utilized to reduce MHD pressure drop in the system. To have a self-consistent ITER design, liquid metal cooling of the divertor and vacuum vessel is considered as well. (C) 1998 Elsevier Science S.A. All rights-reserved.
引用
收藏
页码:669 / 674
页数:6
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