蒸気発生器伝熱管内蓄水量測定実験と蓄水量評価モデル

Experiments of coolant accumulation in SG U tube and analytical model development

山路 達也*; 小泉 安郎; 山崎 康平*; 大竹 浩靖*; 長谷川 浩司*; 大貫 晃*; 金森 大輔*

Yamaji, Tatsuya*; Koizumi, Yasuo; Yamazaki, Kohei*; Otake, Hiroyasu*; Hasegawa, Koji*; Onuki, Akira*; Kanamori, Daisuke*

PWR小破断冷却材喪失事故時に、過渡的な炉心水位低下をもたらすことが懸念されている、蒸気発生器上昇流側U字管内冷却水滞留を調べることを目的として、凝縮を伴う垂直管内気液対向流の蓄水挙動を実験により調べた。実験は、内径18mm、長さ4mの垂直円管を試験流路として、蒸気と水を用いて圧力0.1MPaの下で行われた。透明管による可視化、及び、真鍮管を用いた蓄水量定量評価の2種の実験を行った。流路下端入口で液が流下できない条件であっても、蒸気は流路を上昇するにつれ凝縮されて流速を減じるため、管路上方で凝縮液流下の状態となり、管路内に二相混合水位が形成され、管路内に凝縮水滞留を生じることを実験的に把握した。さらに実験結果をもとに、蓄水量評価モデルを導出し、蓄水挙動を適切に表現できることを確認した。

Experiments of condensing counter-current two-phase flow in a vertical pipe were performed. This study was intended to examine water accumulation in the up-flow side of steam generator U-tubes of a PWR during the reflux cooling stage of a small break LOCA. It has been apprehended that the water accumulation may result in temporary core liquid level depression. The inner diameter and the length of a test flow channel used in the experiments were 18 mm and 4 m, respectively. The experiments were performed by using steam and water at 0.1 MPa. Two kinds of experiments were conducted; visualization experiments by using a transparent test section and quantitative water accumulation evaluation experiments by using a brass test section. Even if water on the inner surface of the test pipe could not flow downward at the lower portion of the test pipe, a part of water became to flow downward at the upper portion of the test pipe since steam velocity decreased because of condensation. Thus, two-phase mixture level was formed in the upper portion of the test pipe, which resulted in the water accumulation in the pipe. The model to predict the water accumulation was proposed. It predicted the water accumulation reasonably well.