ナトリウム冷却炉の上部プレナム流動特性の研究; 水流動試験の検証解析と渦予測手法の適用性検討

Study of hydraulic behavior for reactor upper plenum in sodium-cooled fast reactor; Verification analysis of water experiment and applicability of vortex prediction method

藤井 正; 近澤 佳隆  ; 此村 守; 上出 英樹 ; 木村 暢之; 中山 王克; 大島 宏之; 成田 均*; 藤又 和博*; 糸岡 聡*

Fujii, Tadashi; Chikazawa, Yoshitaka; Konomura, Mamoru; Kamide, Hideki; Kimura, Nobuyuki; Nakayama, Okatsu; Ohshima, Hiroyuki; Narita, Hitoshi*; Fujimata, Kazuhiro*; Itooka, Satoshi*

実用化戦略調査研究で概念設計を進めているナトリウム冷却大型炉では、従来設計よりも高流速条件となる炉上部プレナム内の流動特性を把握するため、縮尺水流動試験が実施されている。本報告では、汎用熱流体解析プログラムを用いて水試験体系を対象とした流動解析を実施し、実機体系でのプレナム内流況と気泡を伴う水中渦の評価に対する適用性を検討した。(1)1/10縮尺プレナム試験を対象に、フルード数一致条件での定常解析を実施した。解析では、炉心上部機構内部から炉容器壁に向かう噴出し流れや、切込み部からの上昇噴流等の上部プレナムでの特徴的なフローパターンを再現できる見通しを得た。また、実機体系での全体流況が水試験体系と定性的に一致することを確認するとともに、解析における数値解法や境界条件等の設定がフローパターンに及ぼす影響が明らかとなった。(2)伸長渦理論に基づく渦予測評価手法を用いて、1/10縮尺試験のディッププレート下方領域における渦の分布を評価した。実機流速一致条件の場合には、水試験と同様、コールドレグ配管壁からホットレグ配管に吸込まれる2本の渦を、気泡を伴う水中渦として同定した。この結果より、上部プレナム内で定常的に発生する液中渦を渦予測評価手法により同定できることを確認した。

A conceptual design study of the sodium-cooled fast reactor is in progress in the Feasibility Study on Commercialized Fast Reactor Cycle Systems. Reduced scale water experiments are being performed in order to clarify the flow pattern in the upper plenum of the reactor which has higher velocity condition than the past design. In this report, the hydraulic analyses of the water experiments using the general-purpose thermal hydraulic analysis program were executed; and the applicability to evaluation of flow pattern and vortex cavitations for the designed reactor was examined. (1) Steady-state analyses under the Froude number similar condition were carried out for the 1/10th reduced scale plenum experiments. Analyses results reproduced the characteristic flow patterns in the upper plenum, such as gushed flow from the inside of the upper internal structure to reactor vessel wall and the jet flow from the slit of the upper internal structure. Further, it was confirmed that the calculated flow pattern of a designed reactor system agreed with that of the water experiment qualitatively. Moreover, the influence which setting of numerical solution and boundary condition etc. in analyzing causes to flow pattern in the plenum became clear. (2) The distribution of the vortices under the dipped plate region in the 1/10th plenum model was evaluated using the prediction method of a submerged vortex which is based on the stretching vortex theory. In case of the same velocity condition as the reactor, it identified the two vortices which were sucked into the hot leg piping from the cold leg piping wall as the submerged vortex cavitations. From this analysis result, it confirmed that the submerged vortex cavitations, which may occur in the reactor upper plenum steadily, could be identified using this prediction method.