2020 Fall Meeting

Presentation information

Oral presentation

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

[1K07-11] Advanced Reactor and Advanced Design Technology of the Reactor Facility

Wed. Sep 16, 2020 2:45 PM - 4:15 PM Room K (Zoom room 11)

Chair:takayuki miyagawa(JAPC)

3:45 PM - 4:00 PM

[1K11] Verification of Evaluation Method of Equipment Response Considering the Dynamic Stiffness at the Support Location

*Yoshihiro Goto1, Takahito Kumagai2, Yugo Hyotani2, Naoki Ojima3 (1. Hitachi, 2. HGNE, 3. HiICS)

Keywords: Three dimensional finite element method, Equipment structure interaction, Dynamic stiffness

In order to evaluate a reasonable acceleration floor response, we focused on the equipment structure interaction method using a dynamic stiffness at the support location. To confirm the applicable frequency range with the method, we compared a vibration response obtained by the model coupling equipment and structure with that obtained by the model using the dynamic stiffness. As a result, the vibration response obtained by the model using the dynamic stiffness and the coupled method were well matched in range of the first floor vibration mode. The difference between the vibration response obtained by the coupled method and the present method may become large under the condition of high order floor vibration modes higher than second mode.