Critical flow modelling in nuclear safety : a state-of-the-art report - OECD Nuclear Energy Agency. Committee on the Safety of Nuclear Installations (Paris: Nuclear Energy Organisation for Economic Co-operation and Development, 1982)
Includes bibliographical references
Keywords: Pressurized water reactors -- -- Loss of coolant -- -- Mathematical models; Pressurized water reactors -- -- Blowdown -- -- Mathematical models; Two-phase flow -- -- Mathematical models