Approach Based On Fa And Ddt Criteria To Evaluate Hydrogen Ignition Risk During Severe Accident in Daya Bay Npp
Modeling Bubble Condenser Containment with Computer Code COCOSYS:Post-Test Calculations of the Main Steam Line Break Experiment at Electrogorsk BC V-213 Test Facility
Managing Technological Challenges For Advanced And Evolutionary Power Reactors At The Technical Center Of Framatome ANP
Stress Analysis And Assessment Of Hermetically Sealed Container For Radioactive Material Transportation
Determining the Residual Lifetime for the Main RBMK Components in Frame of Life Extension of Power Units
Development Of Technologies On Innovative Simplified Nuclear Power Plant Using High-Efficiency Steam Injectors(3) Development of Multi-Stage Steam Injector For Feedwater Heaters Using Two-Phase Flow Analysis
Evaluating Fluid Behavior in Advanced Reactor Systems Using Coupled Computational Fluid Dynamics and Systems Analysis Tools
Evolutionary Engineering Approaches In New Projects Of The Npp With Rmbk-Type Pressure-Tube Power Reactors