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Featured researches published by Yoshito Umeki.


Nuclear Engineering and Technology | 2014

A SEISMIC DESIGN OF NUCLEAR REACTOR BUILDING STRUCTURES APPLYING SEISMIC ISOLATION SYSTEM IN A HIGH SEISMICITY REGION -A FEASIBILITY CASE STUDY IN JAPAN

Tetsuo Kubo; Tomofumi Yamamoto; Kunihiko Sato; Masakazu Jimbo; Yoshito Umeki

A feasibility study on the seismic design of nuclear reactor buildings with application of a seismic isolation system is introduced. After the Hyogo-ken Nanbu earthquake in Japan of 1995, seismic isolation technologies have been widely employed for commercial buildings. Having become a mature technology, seismic isolation systems can be applied to NPP facilities in areas of high seismicity. Two reactor buildings are discussed, representing the PWR and BWR buildings in Japan, and the application of seismic isolation systems is discussed. The isolation system employing rubber bearings with a lead plug positioned (LRB) is examined. Through a series of seismic response analyses using the so-named standard design earthquake motions covering the design basis earthquake motions obtained for NPP sites in Japan, the responses of the seismic isolated reactor buildings are evaluated. It is revealed that for the building structures examined herein: (1) the responses of both isolated buildings and isolating LRBs fulfill the specified design criteria; (2) the responses obtained for the isolating LRBs first reach the ultimate condition when intensity of motion is 2.0 to 2.5 times as large as that of the design-basis; and (3) the responses of isolated reactor building fall below the range of the prescribed criteria.


ASME 2014 Pressure Vessels and Piping Conference | 2014

Development of an Evaluation Method for Seismic Isolation Systems of Nuclear Power Facilities: Part 8 — Fundamental Properties of Full-Scale Lead Rubber Bearings Based on Breaking Test

Nobuhisa Sato; Takashi Nakayama; Takashi Kaneko; Seiji Nagata; Keisuke Kurihara; Hideo Hirai; Ko Mizutani; Yoshito Umeki

This paper provides a part of the series “Development of an Evaluation Method for Seismic Isolation Systems of Nuclear Power Facilities.” This part shows the fundamental properties of full-scale lead rubber bearings with 1600 mm diameter based on break tests. The following results are mainly obtained.One: The deformations and the acting loads of the full-scale specimens were accurately obtained up to break by the measurement system for the break tests.Two: The fundamental properties for the full-scale lead rubber bearings with a large-diameter lead plug were obtained by the basic property tests. The load-displacement relations were stable and similar basic properties were obtained among the specimens.Three: The result of shear break tests showed that the hardening property of the specimens had a certain harmony with the hardening stiffness model which was used in the seismic response analysis to investigate the safety margin for severe earthquakes beyond design basis earthquakes of nuclear power facilities. The effect of axial pressure on hardening property was not specifically observed. The evaluated linear strain limit was larger than 250% for every specimen.Four: The softening property of the specimens was obtained from the tensile break tests. The axial stress of tensile yield was approx. 1.4 MPa and the axial stress did not show any negative gradient at least up to approx. 10% axial strain after the tensile yield even with offset shear strains.Five: The tensile force acting on the bolts which secure the specimen to the testing machine was lower than the estimated tensile force at shear break, which indicates tensile force was conservatively calculated to maintain safety in the design for foundation of lead rubber bearings.Copyright


ASME 2014 Pressure Vessels and Piping Conference | 2014

Development of an Evaluation Method for Seismic Isolation Systems of Nuclear Power Facilities: Part 6 — Scaled Tests to Obtain Basic Characteristics of Lead Rubber Bearing

Tsutomu Hirotani; Ryota Takahama; Masaki Yukawa; Hiroshi Hibino; Yuji Aikawa; Hideo Hirai; Hiroshi Shimizu; Yoshito Umeki

This paper provides a series comprising the “Development of Evaluation Method for Seismic Isolation Systems of Nuclear Power Facilities”. Part 6 presents scaled tests for Lead Rubber Bearing (LRB) newly developed for this project.Following tests are performed to obtain the basic characteristics of LRB,.(1) Horizontal and Vertical Simultaneous Loading Test:LRBs with diameter of 250mm are tested dynamically under simultaneous axial and lateral loading. The hysteresis characteristics is not changed under compressive load although it is changed under tensile load.(2) Basic Break Test:LRBs with a diameter of 800mm are tested statically under various combinations of axial and lateral forces. The hysteresis characteristics model of LRB is determined by this test. It is confirmed that the breaking strain of LRB under compression load exceeds 450%.(3) Horizontal Hardening and Vertical Softening Test:For LRBs with a diameter of 1200 mm, 75% scale of actual LRB are tested statically for horizontal hardening and vertical softening regions. It is confirmed that the hysteresis model which is developed by smaller LRBs is applicable to these large scale models.Copyright


ASME 2014 Pressure Vessels and Piping Conference | 2014

Development of an Evaluation Method for Seismic Isolation Systems of Nuclear Power Facilities: Part 11 — Improvement of the Seismic Isolator Design Method

Yuji Aikawa; Hiroshi Hibino; Yoshitaka Takeuchi; Shingo Asahara; Hideo Hirai; Shinji Kosugi; Shinji Matsuoka; Yoshito Umeki

This paper provides a part of series of “Development of an Evaluation Method for Seismic Isolation Systems of Nuclear Power Facilities”. This part shows improvements of seismic isolator design method applied to nuclear power facilities. The proposed improvement design methods consist of the following two items.One is an improvement of design method for axial stress in a laminated rubber bearing. Largely different natural frequency in vertical and horizontal direction of the seismic isolator may need a special consideration to combine the design seismic loads in different directions. Therefore isolator’s behavior under multiple direction earthquake is studied, and an improved design method is proposed in the axial stress in a laminated rubber bearing.The other is a reasonable design method for seismic isolator joints. A seismic isolator joint is considered to be one of the key factors for assuring seismic integrity of the seismic isolation system for nuclear power facilities. As a series of design method of seismic isolators, evaluation method of axial force of anchor bolts, among various parts of joints, under design level seismic load is studied and improved method is proposed to confirm the structural behavior for a better performance of the system.Copyright


ASME 2014 Pressure Vessels and Piping Conference | 2014

Development of an Evaluation Method for Seismic Isolation Systems of Nuclear Power Facilities: Part 10 — Evaluation of Seismic Isolator Design

Hiroyuki Asano; Tsutomu Hirotani; Takashi Nakayama; Takemi Norimono; Yuji Aikawa; Kunihiko Sato; Shinji Asakura; Masakazu Jimbo; Yoshito Umeki

This paper provides a part of series of “Development of an Evaluation Method for Seismic Isolation Systems of Nuclear Power Facilities”. This part shows an evaluation of seismic isolator design established in this project where several methods are newly developed. The major four accomplishments are as follows.One: establishment of design earthquake specially considered for seismically isolated nuclear power facilities. The design earthquakes are made to fit multiple target spectra with different damping factors considering a building, equipment and seismic isolators for more precise response analyses.Two: design and development of a high-performance seismic isolator. Against the large design earthquakes, a seismic isolator is newly developed which has a large diameter lead plug for more damping; the isolators were actually manufactured and tested.Three: seismic response analyses for seismically isolated nuclear power plants. Light water reactors are designed where the structural characteristics of the seismic isolation system is reflected.Four: evaluation of thermal effects on seismic isolators by a long-duration earthquake. Considering a long-duration earthquake, the heat generation phenomenon in the lead plug is analytically evaluated to ensure the lead plug’s damping performance.By introducing these accomplishments, the realistic design of a seismically isolated nuclear power plant is achieved.Copyright


ASME 2014 Pressure Vessels and Piping Conference | 2014

Development of an Evaluation Method for Seismic Isolation Systems of Nuclear Power Facilities: Part 7 — Breaking Test Plan and Development of Test Machine for Full-Scale Lead Rubber Bearings

Shinji Kosugi; Kenji Kanazawa; Hidekazu Tsudome; Nobuhisa Sato; Masakazu Jimbo; Kunihiko Sato; Yoshito Umeki

This paper is a part of the series “Development of an Evaluation Method for Seismic Isolation Systems of Nuclear Power Facilities.” This part presents a break test plan and development of a test machine for a full-scale lead rubber bearing (LRB). Application of seismic base-isolation systems using LRBs of 1600 mm in diameter to reactor building has been considered for the purpose of enhancing seismic safety. It is important to obtain the ultimate properties of isolators in order to estimate the seismic safety margin of seismic base-isolated structures against a beyond design-basis earthquake events. Recent studies reveal that the scaled effect appears on the ultimate properties of seismic rubber bearings. However, because of the limitation of the loading capabilities of loading machines, the ultimate property of such a large scale LRBs has not been confirmed.In this study, the break tests for LRBs of 1600 mm in diameter is planned on the basis of estimation that refers to previous studies on break tests for small-scale LRBs and natural rubber bearings. The world-largest class test machine is designed and constructed to conduct static break tests for the full-scale LRBs. Furthermore, the performance of the test machine is evaluated from test results including those for break tests.Copyright


Journal of Structural and Construction Engineering (transactions of Aij) | 2017

ULTIMATE PROPERTIES OF LARGE-SCALE LEAD RUBBER BEARING USING FULL-SCALE BREAK TEST

Shinji Kosugi; Kenji Kanazawa; Takafumi Hiraki; Seiji Nagata; Takashi Nakayama; Kunihiko Sato; Masakazu Jimbo; Yoshito Umeki


Journal of Structural and Construction Engineering (transactions of Aij) | 2017

SIMULATION OF ULTIMATE CHARACTERISTICS OF LARGE SCALE SEISMIC ISOLATOR BASED ON LARGE DEFORMATION FINITE ELEMENT ANALYSIS

Takahiro Mori; Nobuo Masaki; Nobuo Murota; Masaki Ikeda; Shinji Kosugi; Hiroshi Shimizu; Masakazu Jimbo; Yoshito Umeki


Journal of Advanced Concrete Technology | 2017

Experimental and Analytical Study of Structural Performance of RC Shear Walls with Corroded Reinforcement

Toshinori Oyamoto; Arinori Nimura; Takashi Okayasu; Shohei Sawada; Yoshito Umeki; Hiroyuki Wada; Tamae Miyazaki


Journal of Advanced Concrete Technology | 2016

Residual Static Strength of Concrete Cylinder Specimen and Stud Anchor Specimen after Cyclic Loadings

Osamu Kontani; Naoki Ishitobi; Junya Kawada; Noriaki Taogoshi; Makoto Koge; Yoshito Umeki

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Kunihiko Sato

Mitsubishi Heavy Industries

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Hiroshi Shimizu

Mitsubishi Heavy Industries

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Kenji Kanazawa

Central Research Institute of Electric Power Industry

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