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Published in 2019 at "Nuclear Engineering and Design"
DOI: 10.1016/j.nucengdes.2019.110357
Abstract: Abstract An analytical model was developed to describe thermal stratification in a primary containment vessel (PCV) and transient thermal-hydraulics coupled with a reactor pressure vessel (RPV) using TRACE code version 5.0 patch level 4. Geometries…
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Keywords:
trace code;
thermal stratification;
pool;