Nuclear-coupled thermal hydraulics stability of a natural circulation lead-cooled fast reactor

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

Stability analyses are carried out for a natural circulation lead-cooled fast reactor which is at its design stage. Because of its natural circulation feature, flow stability as well as nuclearcoupled thermal hydraulics stability is of some concern. Modal Expansion Method (MEM) and Reduced Order Model (ROM) are used for neutronics and thermal hydraulics part, respectively. These two separate models are coupled through feedback effects. Different simulation scenarios on the separate and coupled models are reported..

Original languageEnglish (US)
Title of host publicationNext Generation Reactors and Advanced Reactors; Nuclear Safety and Security
PublisherAmerican Society of Mechanical Engineers (ASME)
ISBN (Electronic)9780791845936
DOIs
StatePublished - Jan 1 2014
Event2014 22nd International Conference on Nuclear Engineering, ICONE 2014 - Prague, Czech Republic
Duration: Jul 7 2014Jul 11 2014

Publication series

NameInternational Conference on Nuclear Engineering, Proceedings, ICONE
Volume3

Other

Other2014 22nd International Conference on Nuclear Engineering, ICONE 2014
CountryCzech Republic
CityPrague
Period7/7/147/11/14

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ASJC Scopus subject areas

  • Nuclear Energy and Engineering

Cite this

Lu, Q., & Uddin, R. (2014). Nuclear-coupled thermal hydraulics stability of a natural circulation lead-cooled fast reactor. In Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security (International Conference on Nuclear Engineering, Proceedings, ICONE; Vol. 3). American Society of Mechanical Engineers (ASME). https://doi.org/10.1115/ICONE22-31070