Open AccessMELCOR 1.8.2 assessment: The DF-4 BWR Damaged Fuel experiment
Author(s) -
Timothy J. Tautges
Publication year - 1993
Language(s) - English
Resource type - Reports
DOI - 10.2172/10110563
Subject(s) - nuclear engineering , cladding (metalworking) , eutectic system , boiling water reactor , environmental science , materials science , engineering , alloy , metallurgy , composite material