2006 · 14 citations · 5 references
EngineeringAerospace EngineeringNuclear EngineeringNuclear Safety AnalysisSafety EngineeringThermal AnalysisFire Safety EngineeringHeat Transfer AnalysisReactor Core DesignThermal DesignThermal SimulationThermal-hydraulic Safety AnalysisCore Safety Margin AnalysisCore Thermal-hydraulic DesignQualificationShielding Safety MarginsThermal Hydraulic AnalysisThermal-hydraulic Code ValidationThermal-hydraulic CodesThermal-hydraulic Design
The advanced thermal-hydraulic subchannel code COBRA-TF has been recently improved and applied for stand-alone and coupled LWR core calculations at the Pennsylvania State University in cooperation with AREVA NP GmbH, Germany and the Technical University of Madrid. To enable COBRA-TF for academic and industrial applications including safety margins evaluations and LWR core design analyses, the code programming, numerics, and basic models were revised and substantially improved. The code has undergone through an extensive validation, verification, and qualification program.
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NUPEC BWR Full-size Fine-mesh Bundle Test (BFBT) Benchmark
D. Neykov, Hideaki UTSUNO, L. E. Hochreiter et al. · OECD Papers · 2006 · 116 citations
Engineering, Computational Engineering, Nuclear Engineering +13
Kostadin Ivanov, Rafael Macián‐Juan, Adi Irani et al. · Annals of Nuclear Energy · 1999 · 24 citations
Engineering, Mechanical Engineering, Nuclear Engineering +12