COUPLED 3-D NEUTRONICS/THERMAL-HYDRAULICS OPTIMIZATION STUDY FOR IMPROVING THE RESPONSE OF A 3600 MW(THERMAL) SFR CORE TO AN UNPROTECTED LOSS-OF-FLOW ACCIDENT
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Date
2013-09Type
- Journal Article
ETH Bibliography
yes
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Publication status
publishedJournal / series
Nuclear TechnologyVolume
Pages / Article No.
Publisher
American Nuclear SocietySubject
Sodium-cooled fast reactor void reactivity; Coupled unprotected; Loss-of-flow accident analysis; Stable sodium boiling; Fast-reactorMore
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ETH Bibliography
yes
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