Open AccessSensitivity Analysis and Failure Damage Domain Identification of the Passive Containment Cooling System of an AP1000 Nuclear Reactor
Author(s) -
Francesco Di Maio,
Giancarlo Nicola,
Yu Yu,
Enrico Zio
Publication year - 2014
Publication title -
hal (le centre pour la communication scientifique directe)
Language(s) - English
Resource type - Conference proceedings
Subject(s) - containment (computer programming) , sensitivity (control systems) , nuclear engineering , loss of coolant accident , coolant , transient (computer programming) , containment building , thermal hydraulics , nuclear reactor , pressurized water reactor , water cooling , reactor pressure vessel , environmental science , cabin pressurization , computer science , engineering , heat transfer , mechanical engineering , accident management , mechanics , electronic engineering , programming language , physics , operating system