Open AccessGeneric BWR-4 degraded core in-vessel study. Status report
Publication year - 1984
Language(s) - Uncategorized
Resource type - Reports
DOI - 10.2172/5913790
Subject(s) - boiler blowdown , scram , boiler feedwater , cabin pressurization , nuclear engineering , transient (computer programming) , pressure vessel , coolant , loss of coolant accident , engineering , environmental science , boiler (water heating) , mechanical engineering , computer science , waste management , inlet , operating system