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Development of numerical simulation system for thermal-hydraulic analysis in fuel assembly of sodium-cooled fast reactor

ナトリウム冷却高速炉燃料集合体熱流動数値シミュレーションシステムの構築

大島 宏之; 上羽 智之; 橋本 昭彦*; 今井 康友*; 伊藤 昌弘*

Ohshima, Hiroyuki; Uwaba, Tomoyuki; Hashimoto, Akihiko*; Imai, Yasutomo*; Ito, Masahiro*

原子力機構では、様々な運転条件下における高速炉燃料集合体内熱流動現象の解明を目的として、3つの熱流動解析プログラムと1つの変形解析プログラムで構成するシミュレーションシステムの開発を進めている。ここでは、システムを構成する各プログラムの数値解析手法と妥当性確認の概要を示す。

A numerical simulation system, which consists of a deformation analysis program and three kinds of thermal-hydraulics analysis programs, is being developed in Japan Atomic Energy Agency in order to offer methodologies to clarify thermal-hydraulic phenomena in fuel assemblies of sodium-cooled fast reactors under various operating conditions including fuel deformation. This paper gives a summary of numerical methods of component programs of the system and their validation studies.

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