Modeling of Flow Blockage in a Liquid Metal-Cooled Reactor Subassembly with a Subchannel Analysis Code
Author:
Affiliation:
1. Korea Atomic Energy Research Institute, P.O. Box 105 Yuseong, Daejeon 305-600, Korea
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT05-A3580
Reference13 articles.
1. The SABRE code for fuel rod cluster thermohydraulics
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3. Applications of the COMMIX code using the porous medium formulation
4. A subchannel analysis code MATRA-LMR for wire wrapped LMR subassembly
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