2022 Annual Meeting

Presentation information

Oral presentation

IV. Nuclear Plant Technologies » 401-3 Reactor Design, Construction and Examination of Nuclear Power Station, Aseismatic Design, Nuclear Ship

[1F01-06] Advanced Design Technology of Reactor Equipment

Wed. Mar 16, 2022 10:15 AM - 12:00 PM Room F

Chair: fumihiko ishibashi (Toshiba ESS)

11:00 AM - 11:15 AM

[1F04] Effect on Buckling Capacity of PWR-CV under Different Input Seismic Waves

*Shinjiro Hidaka1, Kisaburo Azuma1, Gaku Shoji2 (1. NRA, 2. Univ. of Tsukuba)

Keywords:Input seismic wave, Buckling capacity, Containment vessel, Seismic proving test, Static elasto-plastic buckling analysis

Recently, the buckling evaluation of a containment vessel of a PWR reactor containment vessel (PWR-CV) has been performed not only by using the method designated in JEAG4601(hereinafter, design by rule), but also by using elasto-plastic buckling static analysis based on the finite element model (hereinafter, design by analysis).
In the previous study, it was confirmed that the buckling capacity obtained by the design by analysis was about 20% higher than that by the design by rule. However, the effect on the buckling capacity for different input seismic waves used in past shaking table tests has not been investigated in the previous study.
In this study, we created an input seismic wave to focus on the vibration characteristics of the PWR-CV, and investigated the effect of different input seismic waves on the buckling capacity of the PWR-CV.