Open AccessDelayed Neutron Losses in Circulating Fuel Reactors -- MSCR Memo No. 6
Author(s) -
T.W. Kerlin
Publication year - 1961
Language(s) - English
Resource type - Reports
DOI - 10.2172/1512271
Subject(s) - neutron , nuclear engineering , delayed neutron , physics , code (set theory) , nuclear physics , environmental science , mechanics , computer science , neutron temperature , engineering , programming language , set (abstract data type)
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