Study on strength of thin-walled tee pipe for fast breeder reactors under seismic loading

地震荷重下での高速炉用薄肉ティ配管の強度に関する研究

渡壁 智祥; 月森 和之; 大谷 章仁*; 森泉 真; 金子 尚昭*

Watakabe, Tomoyoshi; Tsukimori, Kazuyuki; Otani, Akihito*; Moriizumi, Makoto; Kaneko, Naoaki*

原子炉の耐震安全性の観点から配管の終局的な強度を把握することは重要である。設計地震荷重を超える過酷な入力条件下での高速炉用薄肉ティ配管の破損様式及び終局強度を試験により検証した結果について報告する。

In recent years, earthquakes over design condition were observed in Japan. Confirming the ultimate strength and design safety margin of mechanical components is important for the seismic integrity. This study focused on piping components, and it was one of the most important mechanical components for protecting boundary of coolant. Failure tests of thick-walled piping components for Light Water Reactors (LWRs) described previously in the literature. According to these tests, the failure mode of thick-walled piping components under seismic cyclic loading was low cycle fatigue. However, failure tests have scarcely been performed on thin-walled piping components pressurized at low levels for Fast Breeder Reactors (FBRs). This paper presents dynamic failure tests of thin-walled piping components in FBRs. Based on the test results, the failure mode, the ultimate strength, and the elastic-plastic behavior are discussed.