Concepedia
Annals of Nuclear Energy · 1997 · 25 citations · 3 references
EngineeringAstronomyHeat TransferThermal-hydraulic Safety AnalysisLarge Break Loss Of Coolant Accident ResponseLarge Break Loss-of-coolant AccidentLoss-of-coolant AccidentsThermal-hydraulic Code Validation
3
Two-phase flow phenomena in full-scale reactor geometry
Franz Mayinger, Philipp Weiss, K. Wolfert · Nuclear Engineering and Design · 1993 · 64 citations
Engineering, Computational Engineering, Computational Fluid Dynamics +13
COBRA/RELAP5: A Merged Version of the COBRA-TF and RELAP5/MOD3 Codes
Sang Yong Lee, Jae Jun Jeong, Si-Hwan Kim et al. · Nuclear Technology · 1992 · 38 citations
Engineering, High-performance Computing, Systems Engineering +14
The contribution of UPTF experiments to resolve some scale-up uncertainties in countercurrent two phase flow
H. Glaeser, H. Karwat · Nuclear Engineering and Design · 1993 · 29 citations · Full text
Engineering, Physics, Fluid Dynamics +12