SSTAR: the US lead-cooled fast reactor (LFR)

被引:144
|
作者
Smith, Craig F. [1 ,2 ]
Halsey, William G. [3 ]
Brown, Neil W. [3 ]
Sienicki, James J. [4 ]
Moisseytsev, Anton [4 ]
Wade, David C. [4 ]
机构
[1] Lawrence Livermore Natl Lab, Monterey, CA 93943 USA
[2] USN, Postgrad Sch, Monterey, CA 93943 USA
[3] Lawrence Livermore Natl Lab, Livermore, CA 94550 USA
[4] Argonne Natl Lab, Argonne, IL 60439 USA
关键词
D O I
10.1016/j.jnucmat.2008.02.049
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
It is widely recognized that the developing world is the next area for major energy demand growth, including demand for new and advanced nuclear energy systems. With limited existing industrial and grid infrastructures, there will be an important need for future nuclear energy systems that can provide small or moderate increments of electric power (10-700 MWe) on small or immature grids in developing nations. Most recently, the global nuclear energy partnership (GNEP) has identified, as one of its key objectives, the development and demonstration of concepts for small and medium-sized reactors (SMRs) that can be globally deployed while assuring a high level of proliferation resistance. Lead-cooled systems offer several key advantages in meeting these goals. The small lead-cooled fast reactor concept known as the small secure transportable autonomous reactor (SSTAR) has been under ongoing development as part of the US advanced nuclear energy systems programs. It is a system designed to provide energy security to developing nations while incorporating features to achieve nonproliferation goals, anticipating GNEP objectives. This paper presents the motivation for development of internationally deployable nuclear energy systems as well as a summary of one such system, SSTAR, which is the US Generation IV lead-cooled fast reactor system. (C) 2008 Elsevier B.V. All rights reserved.
引用
收藏
页码:255 / 259
页数:5
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