Naoaki Kaneko
IHI Corporation
Network
Latest external collaboration on country level. Dive into details by clicking on the dots.
Publication
Featured researches published by Naoaki Kaneko.
ASME 2012 Pressure Vessels and Piping Conference | 2012
Satoru Kai; Akihito Otani; Naoaki Kaneko
Conventional response spectrum analysis is used for piping seismic design in Japan. When piping is supported by restraints and structures fixed on multiple buildings or floors, the envelope of the response spectra of all supporting points is typically applied for the piping under multiple excitations. The local vibration mode of long piping is difficult to excite by the far input from the vibrating part, so the analysis will overestimate the response. Considering each input from each building or floor can estimate more reasonable seismic response of the piping. The researches about seismic response analysis by multiple input excitations have been performed since 1960s and the analysis methods are used for piping design in the United State.There are a few experimental researches to verify the validity of the analysis method by multiple excitations. So an excitation test by multiple excitations planned to verify the validity of the application. This current study was performed as a preliminary investigation for the excitation test and it was to obtain the seismic response of a piping model by multiple excitations. Several kinds of analysis methods are compared and the characteristics of them are discussed.Copyright
ASME 2014 Pressure Vessels and Piping Conference | 2014
Satoru Kai; Tomoyoshi Watakabe; Naoaki Kaneko; Kunihiro Tochiki; Makoto Moriizumi; Kazuyuki Tsukimori
Piping in a nuclear power plant is usually laid across several floors of a single building or adjacent buildings, and is supported at many points. As the piping is excited by a large earthquake through multiple supporting points, seismic response analysis by multiple excitations within the range of plastic deformation of piping material is necessary to obtain the precise seismic response of the piping. The verification of the dynamic analysis method of piping under an elastic domain, which is excited by multiple seismic inputs, was performed in our study last year and the correspondence of a piping response between an analysis and an experiment have been confirmed [17][18]. However, few experiments under plastic deformation conditions have been performed to verify the validity of multiple excitation analysis under a plastic deformation range. To obtain better understanding of the behavior of piping under a large seismic input, it is important to investigate the seismic response by multiple excitations and to verify the validity of the analytical method by multiple excitation experiments.This paper reports the validation results of the seismic elastic-plastic time history analysis of piping compared with the results of the shaking test of a 3-dimensional piping model under a plastic deformation range using triple uni-axial shake table. Three directional strains from the analysis and the experiments were compared in order to validate the analysis method. As a result, it is confirmed that the elastic-plastic analysis by time history excitation shows good agreement with the test results.Copyright
ASME 2014 Pressure Vessels and Piping Conference | 2014
Tomoyoshi Watakabe; Kazuyuki Tsukimori; Akihito Otani; Makoto Moriizumi; Naoaki Kaneko
In recent years, earthquakes over design condition were observed in Japan. Confirming the ultimate strength and design safety margin of mechanical components is important for the seismic integrity. This study focused on piping components, and it was one of the most important mechanical components for protecting boundary of coolant. Failure tests of thick-walled piping components for Light Water Reactors (LWRs) described previously in the literature. According to these tests, the failure mode of thick-walled piping components under seismic cyclic loading was low cycle fatigue. However, failure tests have scarcely been performed on thin-walled piping components pressurized at low levels for Fast Breeder Reactors (FBRs).This paper presents dynamic failure tests of thin-walled piping components in FBRs. Based on the test results, the failure mode, the ultimate strength, and the elastic-plastic behavior are discussed.Copyright
ASME 2013 Pressure Vessels and Piping Conference | 2013
Satoru Kai; Tomoyoshi Watakabe; Naoaki Kaneko; Kunihiro Tochiki; Makoto Moriizumi; Kazuyuki Tsukimori
The piping in a nuclear power plant is laid across multiple floors of a single building or two buildings, which are supported at many points. As the piping is excited by multiple-inputs from the supporting points during an earthquake, seismic response analysis by multiple excitations is needed to obtain the exact seismic response of the piping. However, few experiments involving such multiple excitation have been performed to verify the validity of multiple excitation analysis. Therefore, analysis of the seismic design of piping in Japan is performed by the enveloped Floor Response Spectrum (FRS), which covers all floor response spectra at all supporting points. The piping response estimated by enveloped FRS is conservative in most cases compared with the actual seismic response by multiple excitations. To perform rational seismic design and evaluation, it is important to investigate the seismic response by multiple excitations and to verify the validity of the analytical method by multiple excitation test.This paper reports the validation results of the multiple-excitation analysis of piping compared with the results of the multiple excitations shaking test using triple uni-axial shaking table and a 3-dimensional piping model (89.1mm diameter and 5.5mm thickness). Three directional moments from the analysis and the shaking test were compared on the validation. As the result, it is confirmed that the analysis by multiple time history excitation corresponds with the test result.Copyright
Mechanical Engineering Journal | 2016
Tomoyoshi Watakabe; Kazuyuki Tsukimori; Akihito Otani; Makoto Moriizumi; Naoaki Kaneko
Journal of Pressure Vessel Technology-transactions of The Asme | 2018
Satoru Kai; Tomoyoshi Watakabe; Kunihiro Tochiki; Naoaki Kaneko; Kazuyuki Tsukimori; Akihito Otani
The Proceedings of the Dynamics & Design Conference | 2017
Keita Takahashi; Ryoma Kato; Masanori Ando; Hidetsugu Matsuzawa; Yuya Nagata; Naoaki Kaneko
The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2015.23 | 2015
Tomoyoshi Watakabe; Kazuyuki Tsukimori; Akihito Otani; Makoto Moriizumi; Naoaki Kaneko
Dynamics and Design Conference : D & D | 2013
Tomoyoshi Watakabe; Naoaki Kaneko; Shigekazu Aida; Akihito Otani; Kazuyuki Tsukimori; Makoto Moriizumi; Seiji Kitamura
ASME 2013 Pressure Vessels and Piping Conference | 2013
Tomoyoshi Watakabe; Naoaki Kaneko; Shigekazu Aida; Akihito Otani; Makoto Moriizumi; Kazuyuki Tsukimori; Seiji Kitamura