Assessment of tritium effluent from Prototype Generation IV Sodium-cooled Fast Reactor
Sign Up to like & getrecommendations! Published in 2021 at "Annals of Nuclear Energy"
DOI: 10.1016/j.anucene.2021.108334
Abstract: Abstract A tritium transport model for a pool-type sodium cooled fast reactor was developed for estimation of tritium effluents from the Prototype Generation IV Sodium-cooled Fast Reactor (PGSFR). For this purpose, the transport model developed… read more here.
Keywords: cooled fast; sodium cooled; tritium effluent; fast reactor ... See more keywords