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Watakabe, Tomoyoshi; Tsukimori, Kazuyuki; Otani, Akihito*; Moriizumi, Makoto; Kaneko, Naoaki*
Mechanical Engineering Journal (Internet), 3(3), p.16-00054_1 - 16-00054_11, 2016/06
It is important to investigate the failure mode and ultimate strength of piping components in order to evaluate the seismic integrity of piping. Many failure tests of thick wall and high pressure piping for Light Water Reactors (LWRs) have been conducted, and the results suggest that the failure mode that should be considered in the design of a thick wall piping for LWRs under seismic loading is low cycle fatigue. On the other hand, Sodium cooled Fast Reactors (SFRs) is thin wall when compared to LWRs piping. Failure tests of a thin wall piping are necessary because past failure tests for LWRs piping are not enough to discuss failure behavior of a thin wall piping. Therefore, this present work investigated the failure mode and the ultimate strength of thin wall tees.
Watakabe, Tomoyoshi; Tsukimori, Kazuyuki; Otani, Akihito*; Moriizumi, Makoto; Kaneko, Naoaki*
Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 8 Pages, 2015/05
Watakabe, Tomoyoshi; Tsukimori, Kazuyuki; Otani, Akihito*; Moriizumi, Makoto; Kaneko, Naoaki*
Proceedings of 2014 ASME Pressure Vessels and Piping Conference (PVP 2014) (DVD-ROM), 8 Pages, 2014/07
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.
Kai, Satoru*; Watakabe, Tomoyoshi; Kaneko, Naoaki*; Tochiki, Kunihiro*; Moriizumi, Makoto; Tsukimori, Kazuyuki
Proceedings of 2014 ASME Pressure Vessels and Piping Conference (PVP 2014) (DVD-ROM), 10 Pages, 2014/07
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. 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.
Watakabe, Tomoyoshi; Kaneko, Naoaki*; Aida, Shigekazu*; Otani, Akihito*; Tsukimori, Kazuyuki; Moriizumi, Makoto; Kitamura, Seiji
Dynamics and Design Conference 2013 (D&D 2013) Koen Rombunshu (USB Flash Drive), 8 Pages, 2013/08
The piping in a nuclear power plant is laid across multiple floors of a single building or two buildings, which are supported at many anchors. As the piping is excited by multiple inputs from the supporting anchors during an earthquake, seismic response analysis by multiple excitations is needed to obtain the exact seismic response of the piping. However, few tests involving such multiple excitations have been performed to verify the validity of multiple excitation analysis. To perform rational seismic design and evaluation, it is important to investigate the seismic response by multiple excitations and verify the validity of the analysis method by multiple excitation test. This paper reports on the result of the shaking test using triple uni-axial shaking tables and a 3-dimensional piping model.
Kai, Satoru*; Watakabe, Tomoyoshi; Kaneko, Naoaki*; Tochiki, Kunihiro*; Moriizumi, Makoto; Tsukimori, Kazuyuki
Dynamics and Design Conference 2013 (D&D 2013) Koen Rombunshu (USB Flash Drive), 10 Pages, 2013/08
The piping in a nuclear power plant is laid across multiple floors of a single building or multiple buildings which support the piping 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, only a few experiments involving such multiple excitations have been performed to verify the validity of multiple excitation analysis. 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 tests. 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.
Watakabe, Tomoyoshi; Kaneko, Naoaki*; Aida, Shigekazu*; Otani, Akihito*; Moriizumi, Makoto*; Tsukimori, Kazuyuki; Kitamura, Seiji
Proceedings of 2013 ASME Pressure Vessels and Piping Conference (PVP 2013) (DVD-ROM), 8 Pages, 2013/07
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 excitations have been performed to verify the validity of multiple excitation analysis. To perform rational seismic design and evaluation, it is important to investigate the seismic response by multiple excitations and verify the validity of the analysis method by multiple excitation test. This paper reports on the result of the shaking test using triple uni-axial shaking tables and a 3-dimensional piping model.
Kai, Satoru*; Watakabe, Tomoyoshi; Kaneko, Naoaki*; Tochiki, Kunihiro*; Moriizumi, Makoto; Tsukimori, Kazuyuki
Proceedings of 2013 ASME Pressure Vessels and Piping Conference (PVP 2013) (DVD-ROM), 9 Pages, 2013/07
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 excitations have been performed to verify the validity of multiple excitation analysis. To perform rational seismic design and evaluation, it is important to investigate the seismic response by multiple excitations and verify the validity of the analysis method by multiple excitation test. This paper reports the validation result of the multiple excitation analysis of piping compared with the results of the multiple excitations shaking test by using triple uni-axial shaking table and a 3-dimensional piping model (89.1 mm diameter and 5.5 mm thickness).
Watakabe, Tomoyoshi; Kitamura, Seiji; Tsukimori, Kazuyuki; Moriizumi, Makoto*; Miyamoto, Akinori*; Morishita, Masaki
no journal, ,
Piping in a nuclear power plant puts across each floor at the same building or between two buildings, and it has many supported points. Therefore, the piping should be as a model subjected to multiple inputs in seismic analysis, but there isn't almost knowledge concerned with analysis for multiple inputs. In this paper, the analysis by using TDOF model having two supported points, and the shaking test by using U-bend piping test piece having two supported points was performed to investigate response of piping subjected to multiple inputs. As a result, the possibility of response analysis for piping subjected to multiple inputs was confirmed.
Ohara, Takaharu; Ikeda, Makinori; Morishita, Masaki; Miyazaki, Masashi; Shimada, Koji; Moriizumi, Makoto*
no journal, ,
no abstracts in English
Abe, Masato; Moriizumi, Makoto; Ariga, Shinji*; Tsukimori, Kazuyuki
no journal, ,
Snubber is a kind of structures used for supporting piping systems. This structure moves smoothly by slow movements like thermal expansion of pipes, but it holds pipes strongly against rapid movements like earthquake. When the oil snubber is used in a plant, its length is adjusted by using an extended pipe. Therefore, its shape is relatively slender. Consequently, compression buckling due to seismic load should be prohibited in the design. In this paper the buckling behaviors obtained by the axial compression test using the snubber test models are described.
Tsukimori, Kazuyuki; Moriizumi, Makoto; Ariga, Shinji*; Abe, Masato
no journal, ,
Snubber is a kind of structures used for supporting piping systems. This structure moves smoothly by slow movements like thermal expansion of pipes, but it holds pipes strongly against rapid movements like earthquake. When the oil snubber is used in a plant, its length is adjusted by using an extended pipe. Therefore, its shape is relatively slender. Consequently, compression buckling due to seismic load should be prohibited in the design. In this paper the detailed analysis results of backing of the snubber test models and the evaluation method of this type of buckling are described.
Tsukimori, Kazuyuki; Moriizumi, Makoto; Abe, Masato; Sadahiro, Daisuke*; Ishigaki, Yoshinobu*
no journal, ,
The elastic limit and the collapse load of a rectangular or circular cross-section beam subjected to both bending moment and shear force are derived analytically with partially approximation. According to the result, there is no interaction between bending moment and shear force in the region of elastic, however, there is an interaction between them with some relation, which is complicated but seems to be close to oval shape. The validity of this relation is examined by FEM analysis.
Abe, Masato; Watakabe, Tomoyoshi; Moriizumi, Makoto*; Tsukimori, Kazuyuki
no journal, ,
The seismic load which occurs to the equipment and piping at the time of an earthquake in nuclear power plants has the various conditions. As for the load direction, it is not certain when earthquake condition. In this paper, a result of analytical evaluation of impact on structural strength of a thin wall elbow is reported, for the purpose of contribute to structural integrity evaluation of the thin wall piping.
