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Showing papers by "James J. Sienicki published in 2018"


Proceedings ArticleDOI
24 Oct 2018
TL;DR: In this article, the results of the coupled control analysis of a sCO2 cycle for a 100 MWe sodium-cooled fast reactor were presented, and the plant control mechanisms were investigated and optimized for load following operation.
Abstract: Supercritical carbon dioxide Brayton cycle power converters can benefit advanced nuclear reactors, as well as small modular reactors, by reducing the plant cost and increasing plant electrical output. The sCO2 cycles can also be designed for operation under direct dry air cooling. This paper presents the results of the coupled control analysis of a sCO2 cycle for a 100 MWe sodium-cooled fast reactor. The plant control mechanisms were investigated and optimized for load following operation.

6 citations


ReportDOI
14 Sep 2018
TL;DR: In this article, the authors present a survey of the state-of-the-art methods and tools for data collection............................................................................................................................... 1 EXECUTIVE SUMMARY
Abstract: .............................................................................................................................. 1 EXECUTIVE SUMMARY ........................................................................................................ 4

6 citations



Proceedings ArticleDOI
24 Oct 2018
TL;DR: In this article, the results of coupled control analysis of a sCO2 cycle for a 100 MWe sodium-cooled fast reactor under changing ambient air temperatures are presented, and the optimum plant operation modes are identified.
Abstract: Supercritical carbon dioxide Brayton cycle power converters can benefit advanced nuclear reactors, as well as small modular reactors, by reducing the plant cost and increasing plant electrical output. The sCO2 cycles can also be designed for operation under direct dry air cooling. The paper presents the results of the coupled control analysis of a sCO2 cycle for a 100 MWe sodium-cooled fast reactor under changing ambient air temperatures. The optimum plant operation modes are identified.

3 citations


Journal ArticleDOI
TL;DR: The FASt TEst Reactor (FASTER) is a sodium-cooled fast spectrum test reactor design that was developed as part of an advanced demonstration and test reactor study, and provides high levels of fast and thermal neutron flux for scientific research and development as discussed by the authors.

1 citations