Development of integrated numerical analysis model for unsteady phenomena in upper plenum and hot-leg piping system of Japan Sodium-cooled Fast Reactor

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Japan Atomic Energy Agency, O-arai, Ibaraki, Japan [1 ]
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ASME Pressure Vessels Piping Div. Publ. PVP |
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Compilation and indexing terms; Copyright 2025 Elsevier Inc;
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摘要：
Flow fields - Fluid structure interaction - Navier Stokes equations - Sodium-cooled fast reactors - Computational fluid dynamics - Reynolds number
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