The advanced high-temperature reactor: high-temperature fuel, liquid salt coolant, liquid-metal-reactor plant

被引:71
|
作者
Forsberg, C [1 ]
机构
[1] Oak Ridge Natl Lab, Oak Ridge, TN 37831 USA
关键词
high-temperature reactor; molten salt coolant; liquid salt coolant; hydrogen;
D O I
10.1016/j.pnucene.2005.05.002
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 Advanced High-Temperature Reactor is a new reactor concept that combines four existing technologies in a new way: (1) coated-particle graphite-matrix nuclear fuels (traditionally used for helium-cooled reactors), (2) Brayton power cycles, (3) passive safety systems and plant designs from liquid-metal-cooled fast reactors, and (4) low-pressure liquid-salt coolants with boiling points far above the maximum coolant temperature. The new combination of technologies enables the design of a large [2400- to 4000-MW(t)] high-temperature reactor, with reactor-coolant exit temperatures between 700 and 1000 C (depending upon goals) and passive safety systems for economic production of electricity or hydrogen. The AHTR [2400-MW(t)] capital costs have been estimated to be 49 to 61% per kilowatt (electric) relative to modular gas-cooled [600-MW(t)] and modular liquid-metal-cooled reactors [1000-MW(t)], assuming a single AHTR and multiple modular units with the same total electrical output. Because of the similar fuel, core design, and power cycles, about 70% of the required research is shared with that for high-temperature gas-cooled reactors. (C) 2005 Elsevier Ltd. All rights reserved.
引用
收藏
页码:32 / 43
页数:12
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