Open AccessDesign of fast flux test facilities for 710 fuel elements based on a neutron filter
Author(s) -
Not Given Author
Publication year - 1968
Language(s) - English
Resource type - Reports
DOI - 10.2172/4331069
Subject(s) - nuclear engineering , neutron flux , flux (metallurgy) , filter (signal processing) , neutron , test (biology) , nuclear physics , computer science , physics , materials science , engineering , electrical engineering , geology , metallurgy , paleontology