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Report No.
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Numerical simulation of flow field in wire-wrapped fuel pin bundle of sodium cooled fast reactor using "SPIRAL"

Ohshima, Hiroyuki; Imai, Yasutomo*

A numerical simulation of flow field in a wire-wrapped fuel pin bundle of fast breeder reactor was carried out using a finite element method code SPIRAL under typical operating conditions. In this simulation, the influence of computational mesh scheme on the result and the prediction characteristics of three kinds of high Reynolds number turbulence models, modified k-e model, RNG k-e model and algebraic stress model, were clarified. SPIRAL was also applied to simulate a flow field in a wire-wrapped 19-pin bundle and its result was compared with available experimental data. The predicted distributions of axial flow through the subchannels, cross flow between fuel pins and swirl flow along the wrapper tube wall caused by the existence of wire-spacer were in good agreement with measured ones.

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