Title of article :
SSTAR: The US lead-cooled fast reactor (LFR)
Author/Authors :
Smith، نويسنده , , Craig F. and Halsey، نويسنده , , William G. and Brown، نويسنده , , Neil W. and Sienicki، نويسنده , , James J. and Moisseytsev، نويسنده , , Anton and Wade، نويسنده , , David C.، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2008
Pages :
5
From page :
255
To page :
259
Abstract :
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.
Journal title :
Journal of Nuclear Materials
Serial Year :
2008
Journal title :
Journal of Nuclear Materials
Record number :
1367216
Link To Document :
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