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Research Areas

Thermal-Fluid Models for Specialized Geometries

PNNL developed the COBRA and VIPRE codes for nuclear reactor core coolant models. COBRA-SFS is the internationally recognized code for spent fuel assembly storage system thermal modeling, and the laboratory is currently modeling systems for defense spent fuel storage at the Hanford Site and modeling commercial spent fuel storage systems in support of the Nuclear Regulatory Commission. Codes incorporate forced and natural convection as well as conductive and radiative heat transfer models for thorough and accurate characterization of these complex thermal/fluid systems.

Experimental and Computational Engineering

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