Shinichi Matsuura
Central Research Institute of Electric Power Industry
Network
Latest external collaboration on country level. Dive into details by clicking on the dots.
Publication
Featured researches published by Shinichi Matsuura.
Nuclear Engineering and Design | 1993
Hiroshi Akiyama; Hideomi Ohtsubo; Hideharu Nakamura; Shinichi Matsuura; Yutaka Hagiwara; Tetsuo Yuhara; Hiroshi Hirayama; Kunio Kokubo; Yuji Ooka
Abstract Central Research Institute of Electric Power Industry (Japan), commissioned by the Ministry of International Trade and Industry, is carrying out the Demonstration Test and Research Program of Buckling of FBR (FY 1987-FY 1993). The first half of the research program was finished after establishing a seismic buckling design guideline (a tentative draft). The purpose of this paper is to describe the dynamic buckling characteristics of FBR main vessels and the outline of the rationalized buckling design guideline for seismic loadings.
Nuclear Engineering and Design | 1995
Shinichi Matsuura; Hideharu Nakamura; Kunio Kokubo; S. Ogiso; Hideomi Ohtsubo
Abstract The purpose of this paper is to describe the computation results and the knowledge of the buckling analysis strategy. Since fast breeder reactor main vessels are thin shell structures, plastic shear-bending buckling is one of the most important problems. To clarify the buckling behaviour, we carried out many tests and numerical calculations. Based on the experience of those buckling analyses, available elements, mesh division, modelling of shape imperfections etc. are described. These results show that the numerical analysis can be a useful tool for evaluating buckling phenomena.
Journal of Pressure Vessel Technology-transactions of The Asme | 2014
Yinsheng Li; Kunio Hasegawa; Michiya Sakai; Shinichi Matsuura; Naoki Miura
When a crack is detected in a nuclear piping system during in-service inspections, failure estimation method provided in codes such as ASME Boiler and Pressure Vessel Code Section XI or JSME Rules on Fitness-for-Service for Nuclear Power Plants can be applied to evaluate the structural integrity of the cracked pipe. In the current codes, the failure estimation method for circumferentially cracked pipes is applicable for both bending moment and axial force due to pressure. Torsion moment is not considered. Recently, two failure estimation methods for circumferentially cracked pipes subjected to combined bending and torsion moments were proposed based on analytical investigations on the limit load for cracked pipes. In this study, experimental investigation was conducted to confirm the applicability of the failure estimation method for cracked pipes subjected to bending and torsion moments. Experiments were carried out on 8-in. diameter Schedule 80 stainless steel pipes containing a circumferential surface crack. Based on the experimental results, the proposed failure estimation methods were confirmed to be applicable to cracked pipes subjected to combined bending and torsion moments.
ASME 2014 Pressure Vessels and Piping Conference | 2014
Michiya Sakai; Ryo Morita; Shinichi Matsuura; Fumio Inada; Shigenobu Onishi; Mitsuo Kugimoto
The earthquake-proof safety of piping systems with local wall thinning due to liquid droplet impingement erosion (LDI) was evaluated using a hybrid experiment which has been incorporated a numerical analysis of the whole system with a static loading test of elbow pipe model. Seismic performance effects of wall thinned elbow were clarified by comparing three cases of different thickness elbow models such as no defect, 50% defect and 75% defect. No damage was observed for in-plane and out-of-plane bending of elbows in the 75% condition under a seismic load equal to five times the design basis earthquake required to reach allowable stress level. In addition, torsion buckling occurred and through wall crack penetrated by cyclic loading under eight times large amplitude the above mentioned seismic motion.Copyright
Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications | 2013
Michiya Sakai; Shinichi Matsuura; Fumio Inada
Pipe wall thinning is a one of the major degradation mechanisms in aged nuclear power plants (NPPs). In Japan, the seismic safety of wall thinning piping system during earthquake must be evaluated in aged NPPs. Seismic safety of piping systems with wall thinning had been investigated by other researchers using shaking table tests of reduced scale and numerical analyses. However, there exist the limitations such as the scale effect of pipe model for shaking table tests and the limit of the evaluation for numerical analysis concerning the criteria of pipe integrity. By the way, elbow can be one of the most important elements to evaluate the seismic safety of piping system. So, in order to evaluate seismic safety of piping systems with wall thinning elbow, hybrid tests have been conducted, in which the seismic response of the whole piping system is treated as a numerical model, and the real piping is used only for the element on which the transformation and damage locally concentrated. The through-wall crack only occurred in the case of a uniform thinning model although cracks didn’t penetrate in the non thinning model and the local thinning model. In the experimental condition, the failure mode of wall thinning elbow under seismic loadings had been low cycle fatigue, and effectiveness of this evaluation method has been demonstrated.© 2013 ASME
ASME 2013 Pressure Vessels and Piping Conference | 2013
Yinsheng Li; Kunio Hasegawa; Michiya Sakai; Shinichi Matsuura; Naoki Miura
When a crack is detected in a nuclear piping system during in-service inspections, the failure estimation method provided in codes such as the ASME Boiler and Pressure Vessel Code Section XI or JSME Rules on Fitness-for-Service for Nuclear Power Plants can be applied to evaluate the structural integrity of the cracked pipe. In the current codes, the failure estimation method for circumferentially cracked pipes includes bending moment and axial force due to pressure. Torsion moment is not considered.The Working Group on Pipe Flaw Evaluation for the ASME Boiler and Pressure Vessel Code Section XI is developing guidance for combining torsion load within the existing solutions provided in Appendix C for bending and pressure loadings on a pipe. A failure estimation method for circumferentially cracked pipes subjected to general loading conditions including bending moment, internal pressure and torsion moment with general magnitude has been proposed based on analytical investigations on the limit load for cracked pipes. In this study, experimental investigation was conducted to confirm the applicability of the proposed failure estimation method. Experiments were carried out on 8-inch diameter Schedule 80 stainless steel pipes containing a circumferential surface crack. Based on the experimental results, the proposed failure estimation method was confirmed to be applicable to cracked pipes subjected to combined bending and torsion moments.Copyright
ASME 2011 Pressure Vessels and Piping Conference: Volume 6, Parts A and B | 2011
Ryo Morita; Fumio Inada; Michiya Sakai; Shinichi Matsuura; Shigenobu Onishi; Mitsuo Kugimoto
For seismic safety evaluation of piping system with local thinning surface by liquid droplet impingement erosion (LDI), hybrid seismic tests were conducted to the piping with a locally-thinned elbow. In this paper, a method for predicting the thinning shape by LDI on the elbow is developed. To determine the thinning shape by LDI, droplet behavior at the elbow is calculated for various flow conditions and geometries. With the calculation of the collision point and velocity for each droplet, collision frequency and average collision velocity on the elbow are estimated. Then, the thinning shape on the elbow is determined with the relationship between the flow conditions and thinning rate. Finally, the evaluated thinning shape is compared with an actual LDI case for the validation of the method.Copyright
ASME 2009 Pressure Vessels and Piping Conference | 2009
Yusuke Sato; Yukihiro Toyoda; Shinichi Matsuura; Michiya Sakai
This study discusses the strength of jointed pipes used underground for fire protection at a nuclear power plant and their capacity to accommodate ground displacement. For this purpose, bending tests, a finite element analysis and an elastic beam theory analysis were conducted. The bending tests were conducted for four types of joints previously subjected to actual use, including welded, flange, screw and coupling types. The welded and flange joints demonstrated significantly higher load capacity; five times that of the coupled joint. The bending test results for the flange, screw and coupling joints were applied to identify the bending moment and rotation angle at the moment the internal pressure reached the level of the atmospheric pressure due to leakage. The limit state of the welded joint was not obtained in the experiment but was estimated by nonlinear finite element analysis. The bending moment and rotation angle of the welded joint were identified at the moment the welded joint reached the limit state. Finally, the test results and finite element analysis were applied to estimate the capacity of each joint to accommodate ground displacement. The elastic beam theory was used by modeling the pipe as an elastic beam and idealizing the joint as an elastic rotational spring. Consequently, the ground displacement capacity of the welded joint exceeded that of the coupling and screw joints by more than 500 per cent.Copyright
ASME 2016 Pressure Vessels and Piping Conference | 2016
Ichiro Tamura; Shinichi Matsuura; Ryuya Shimazu
Jsme International Journal Series B-fluids and Thermal Engineering | 1993
Shinichi Matsuura; Hideharu Nakamura; Seitaro Ogiso; Toshiaki Murakami; Yoji Kawamoto