Capability of Moderator as Heat Sink During Transient for a Natural Circulation Channel Type Boiling Water Reactor
The Amount of Hydrogen Generation and Radionuclides Releases during Severe Accidents of a Pressurized Water Reactor
Development of Internal CRD for Next Generation BWR - Endurance and Robustness Tests of Ball-Bearing Materials in High-Pressure and High-Temperature Water -
Thermal-hydraulic Responses during PWR Pressure Vessel Upper Head Small Break LOCA Based on LSTF Experiment and Analysis
Results of the QUENCH-L1, DISCO-L1,and COMET-L1 Experiments Performed Within the LACOMERA Project at the Forschungszentrum Karlsruhe
Experimental Campaign and Numerical Analysis for the In-Pool Energy Removal System for Emergency Operation
Ratcheting Behavior of 3d Piping System Under Internal Pressure and Seismic Load-Experiment and Analysis