ANALYSES AND COMPUTER CODE DEVELOPMENTS FOR ACCIDENT-INDUCED THERMOHYDRAULIC TRANSIENTS IN WATER-COOLED NUCLEAR REACTOR SYSTEMS. ANALYSES AND COMPUTER CODE DEVELOPMENTS FOR ACCIDENT-INDUCED THERMOHYDRAULIC TRANSIENTS IN WATER-COOLED NUCLEAR REACTOR SYSTEMS.
Data source
Japan Atomic Energy Agency's Library Catalog
A search system for the collections of the Japan Atomic Energy Agency central library. Books, reports, meeting materials, magazines and dockets collected by the library are searchable.
Last updated
June 18, 2026