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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作者：

Japan Atomic Energy Agency, O-arai, Ibaraki, Japan ^{[1
]}

不详 ^{[2
]}

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来源：

ASME Pressure Vessels Piping Div. Publ. PVP |

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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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