Papers

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MELCOR Validation Study on Sodium Pool Fire Model with Comparison to SPHINCS

David L.Y. Louie (Sandia), Mitsuhiro Aoyagi (Japan Atomic Energy Agency)

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DASSH: An Open-Source, Full-Core Subchannel Code for Fast Reactor Design and Analysis

Milos Atz (ANL), Florent Heidet (ANL)

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Study on Hydraulic Characteristics in KAERI 61-PIN Wire-Wrapped Fuel Assembly Using STAR-CCM+ and ANSYS CFX

Gi-Uk Choi (Gachon Univer.), Jonggan Hong (KAERI), Yo-Han Jung (KAERI), Jae-Ho Jeong (Gachon Univer.)

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Prediction of Pressure Drop in Wire-Wrapped Fuel Assemblies with Blocked Channels Using Large Eddy Simulation

D.R. Shaver (ANL), E. Merzari (ANL), L. Brockmeyer (ANL), D. Dai (ANL)

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Validation of Thermal-Hydraulic Data Verification in a 37-Pin Fuel Assembly of PLANDTL Facility Using STAR-CCM+

Gi-Uk Choi (Gachon Univer.), Jae-Ho Jeong (Gachon Univer.)

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