F-1703 機器・配管系の地震時許容基準の検討(S59-1 規格基準の高度化に関連する研究・開発状況(1))(S59 規格基準の高度化に関連する研究・開発状況)

概要

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In order to clarify the design margin of current seismic design margin in nuclear power plant piping, experimental and analytical investigations have been made on the elasto-plastic behavior of piping materials and components. As a result, it became clear that piping component failure was due to low-cycle fatigue that accompanies ratchet. Moreover, piping system model test and analytical study have been performed to establish the rational seismic design allowable stress code. In this paper, the Monotonic Deflection Static Load test results and the Static-cyclic test result for 2-dimentional piping are discussed.
2001-08-22