2023 Annual Meeting

Presentation information

Oral presentation

III. Fission Energy Engineering » 302-1 Advanced Reactor System

[1L15-17] Design Technology for Advanced Reactor 2

Mon. Mar 13, 2023 4:40 PM - 5:30 PM Room L (13 Bildg.2F 1323)

Chair:Tomomi Otani(MFBR)

4:55 PM - 5:10 PM

[1L16] Development of failure mitigation technologies for improving resilience of nuclear structures

(21) Study on buckling and post-buckling behavior of cylinders for failure consequence mitigation under excessive seismic load

*Sho Hasegawa1, Yiji Ye1, Masakazu Ichimiya1, Naoto Kasahara1 (1. UTokyo)

Keywords:Buckling, Post-buckling behavior, Vibration load, Failure consequence mitigation, FEM analyses

Buckling may occur on reactor vessels under excessive seismic load. It is valuable for failure consequence mitigation to clarify post-buckling behavior. In order to investigate buckling and post-buckling behavior of cylinders under vibration load, authors conducted shaking table tests and FEM analyses of cylindrical specimens which simulate reactor vessels.