Critical Heat Flux of Counter-Current Two-Phase Flow of Water and Steamn In Vertical-Narrow-Annular Flow Passages
Use of a CFD-Tool for assessment of the Reactor Pressure Vessel Integrity in Pressure Thermal Shock conditions.Thermal-Hydraulic studies of a Safety Injection in a PWR plant
Development of the Lungman Abwr Engineering Simulator With Relap5-3d and Associated Application to Fwlb Licensing Blowdown Analysis
Engineering Test of Stripping Performance by Multi-centrifugal Contactors System for Spent Nuclear Reprocessing
The HELIO Code Prediction of the Hydrogen Accumulation Incident in the Non-Vented Pipeline of the Hamaoka NPP