2019 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

[2L07-11] Inspection and Safety Evaluation Technology of Nuclear Power Plants

Thu. Mar 21, 2019 2:45 PM - 4:10 PM Room L (Common Education Bildg. 2 3F No.36)

Chair:Takashi Matsunaga(NFI)

3:45 PM - 4:00 PM

[2L11] Development of seismic assessment method for FR core

(4) Seismic experiment and analysis of hexagonal bundle model using deformed core assembly mock-up

*Shinichiro Matsubara1, Akihisa Iwasaki1, Kazuteru Kawamura1, Tomohiko Yamamoto3, Hidenori Harada2 (1. MHI, 2. MFBR, 3. JAEA)

Keywords:FR, three-dimensional, core seismic, group vibration, core deformation

A core seismic analysis method for FR has been developed to evaluate 3D core vibration behavior considering fluid structure interaction and vertical displacements (rising).
In this presentation, the analysis model to consider the influence of core element deformation due to heat and irradiation was verified by comparing the seismic test which used deformed core assembly mock-ups and analysis results.