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Investigation of temperature gradient characteristics for thermal stratification interface in upper plenum of fast reactors

高速炉上部プレナムにおける温度成層化界面の温度勾配特性に関する検討

大野 修司; 菅原 章博*; 大木 裕*; 大島 宏之

Ohno, Shuji; Sugahara, Akihiro*; Oki, Hiroshi*; Ohshima, Hiroyuki

高速炉の原子炉上部プレナムで生じる温度成層化挙動の基本特性を調べるために、典型的な炉上部プレナム体系を基準とした数値実験を実施した。FLUENTコードVer.6.3とRNG型k-$$varepsilon$$乱流モデルを使用し、ナトリウムの流量・温度条件や体系サイズを仮想的に変更して温度成層化解析を行った結果、ナトリウムのプレナム内部平均上昇流速及びナトリウム温度差の条件が成層界面温度勾配の支配因子となることを明らかにした。また、成層界面温度勾配を精度良く予測するためには、界面内部の鉛直方向計算格子分割が重要であることを示した。

Parametric analyses were carried out as numerical experiments to clarify the basic characteristics of thermal stratification behavior in upper plenum of fast reactors. The analyses were performed changing hypothetically the analytical conditions of sodium flow rate, sodium temperature, and the size of analyzed upper plenum, by using a commercial CFD code FLUENT Ver. 6.3 and the RNG k-$$varepsilon$$ turbulence model. The results provided the suggestion that the averaged sodium ascending velocity in the reactor upper plenum region and the sodium temperature difference before and after the transient initiation would be the dominant factors to determine temperature gradient of thermal stratification interface. Further, it was implied that appropriate spatial mesh arrangement in vertical direction around the stratification interface is significant to obtain the accurate numerical solution of interface temperature gradient.

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