Amount of water injection assumed in MAAP analysis for Unit-2
5-1-3 Reactor processes modelling
Investigations concerning the estimation of core and in-containment conditions
Assessment of core status of TEPCO's Fukushima daiichi nuclear power plants (47) - validation of the SAMPSON/MCRA code against the CORA-18 experiment
Assessment of core status of TEPCO's Fukushima daiichi nuclear power plants (44) - sensitivity analysis of flow blockage under severe accident conditions using SAMPSON code
Assessment of core status of TEPCO's Fukushima daiichi nuclear power plants (43) - CFD analysis of steam condensation in the Fukushima Dai-ichi Nuclear Power Plant pressure
Core damage ratio of Unit 1 to 3 of Fukushima Daiichi Nuclear Power Station (Reference)