High power density self-cooled lithium-vanadium blanket

被引:27
作者
Gohar, Y [1 ]
Majumdar, S [1 ]
Smith, D [1 ]
机构
[1] Argonne Natl Lab, Fus Power Program, Argonne, IL 60439 USA
关键词
first wall; blanket; lithium; vanadium; neutronics; spectral shifter; liquid metal blanket design;
D O I
10.1016/S0920-3796(00)00279-9
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
A self-cooled lithium-vanadium blanket concept capable of operating with 2 MW/m(2) surface heat flux and 10 MW/m(2) neutron wall loading has been developed. The blanket has liquid lithium as the tritium breeder and the coolant to alleviate issues of coolant breeder compatibility and reactivity. Vanadium alloy (V-4Cr-4Ti) is used as the structural material because it can accommodate high heat loads. Also, it has good mechanical properties at high temperatures, high neutron fluence capability, low degradation under neutron irradiation, good compatibility with the blanket materials, low decay heat, low waste disposal rating, and adequate strength to accommodate the electromagnetic loads during plasma disruption events. Self-healing electrical insulator (CaO) is utilized to reduce the MHD pressure drop. A poloidal coolant flow with high velocity at the first wall is used to reduce the peak temperature of the vanadium structure and to accommodate high surface heat flux. The blanket has a simple geometrical configuration and low coolant pressure to reduce the fabrication cost, to improve the blanket reliability, and to increase confidence in its performance. Spectral shifter and reflector are utilized to improve the blanket shielding capability and energy multiplication, and to reduce the radial blanket thickness. Natural lithium is used to avoid extra cost related to the lithium enrichment process. (C) 2000 Published by Elsevier Science B.V.
引用
收藏
页码:551 / 558
页数:8
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