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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

Fundamental validation of simulation method for thermal stratification in upper plenum of fast reactor

大野 修司; 大木 裕*; 菅原 章博*; 大島 宏之

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

実用化高速炉の原子炉上部プレナムにおける温度成層化現象を高精度で評価するための手法整備の一環として、多次元熱流動解析コードAQUAと商用CFDコードによる基礎的体系下の水試験の解析を実施した。解析値と試験測定値の比較から、鉛直方向計算格子幅を適正化することで解析コードによらず成層界面の形成・上昇・揺動挙動及び界面温度勾配を適切に予測できることを示した。乱流モデルに標準k-e, RNG k-e及びRSMを適用した場合の比較では、いずれのモデルともに成層化の基本現象をおおむね再現した。

Three-dimensional thermal-hydraulic analyses of thermal stratification phenomena have been carried out in order to validate simulating ability of a single-phase thermal hydraulic code AQUA and commercial CFD codes STAR-CD and FLUENT. The analyses of thermal stratification water experiments demonstrated that the codes reproduced temperature gradient and upward movement of the stratification interface in the case of utilizing appropriate discretization method and computational mesh arrangement for gravitational direction. No remarkable difference was observed between the calculated results with three codes. It was also shown that three turbulence models of the standard k-e model, the RNG k-e model and the RSM predicted fairly well the fundamental stratification behavior observed in the experiments.

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