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高速炉上部プレナム内温度成層化に関する解析手法の基本検証; ナトリウム試験の解析

Fundamental validation of simulation method for thermal stratification in upper plenum of fast reactors; Analysis of sodium experiment

大野 修司; 菅原 章博*; 大木 裕*; 大島 宏之

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

実用化高速炉の原子炉上部プレナム内温度成層化現象に関する解析評価手法整備の一環として、軸対称体系下で行われた温度成層化ナトリウム試験の解析を実施した。CFDコードを用いた3次元解析と試験測定値の比較から、RANS型乱流モデルを使用して温度成層化界面の温度勾配や上昇挙動など基本的な現象を良好に解析できることを示した。また、標準$$k$$-$$varepsilon$$, RNG$$k$$-$$varepsilon$$及びRSMの3つの乱流モデルに関して、モデルの違いが現象の予測性へ及ぼす影響を明らかにした。

Three-dimensional thermal-hydraulic analyses have been carried out for a sodium experiment in a relatively simple axis-symmetric geometry using a commercial CFD code in order to validate simulating methods for thermal stratification behavior in an upper plenum of sodium-cooled fast reactor. Detailed comparison between simulated results and experimental measurement has demonstrated that the code reproduced fairly well the fundamental thermal stratification behaviors such as vertical temperature gradient and upward movement of a stratification interface when utilizing high-order discretization scheme and appropriate mesh size. Furthermore, the investigation has clarified the influence of RANS type turbulence models on phenomena predictability; i.e. the standard $$k$$-$$varepsilon$$ model, the RNG $$k$$-$$varepsilon$$ model and the Reynolds Stress Model.

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