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Dive into the research topics where Masayuki Ishiwata is active.

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Featured researches published by Masayuki Ishiwata.


Nuclear Engineering and Design | 1999

Fracture behavior of carbon steel pipe with local wall thinning subjected to bending load

Katsumasa Miyazaki; Satoshi Kanno; Masayuki Ishiwata; Kunio Hasegawa; Soek Hwan Ahn; Kotoji Ando

To evaluate the structural integrity of power plant piping, monotonic bending tests are conducted on 4- and 3.5-in. diameter full-scale carbon steel pipe specimens with local wall thinning. The local wall thinning is simulated as erosion/corrosion metal loss. The eroded area of the wall thinning is subjected to tensile or compressive stress by applied bending moment. The deformations or fracture behaviors at maximum moments are found to be classified into three types. When the eroded area is subjected to tensile stress, ovalization or crack initiation/growth occurs at the maximum moment. When an eroded area is subjected to compressive stress, ovalization or local buckling occurs. The occurrence of ovalization, crack initiation/growth, or local buckling depends on the initial size of local wall thinning. From the relationships among ovalization, crack growth and local buckling, allowable sizes for local wall thinning are proposed.


Nuclear Engineering and Design | 2002

Fracture behavior of straight pipe and elbow with local wall thinning

Seok-Hwan Ahn; Ki-Woo Nam; Yeon-Sik Yoo; Kotoji Ando; Su-Hwan Ji; Masayuki Ishiwata; Kunio Hasegawa

Abstract Fracture behavior of pipes with local wall thinning is very important for the integrity of nuclear power plant. Then we studied the fracture behavior of straight pipe and elbow with local wall thinning. For the straight pipe, failure mode, limit load and allowable wall thinning limit based on plastic deformation ability have been studied systematically. Twenty two straight pipe specimens were tested. The failure mode was divided into four types; cracking, local buckling, ovalization and plastic collapse (ovalization+buckling). Maximum load was successfully evaluated using plastic section modulus and modified flow stress, in dependent to failure mode. For the elbow, plastic collapse and low cycle fatigue fracture by reversed loading have been tested using ten specimens. Observed failure modes were ovalization and local buckling under monotonic loading, and were local buckling and cracking under cyclic loading, especially local buckling promoted crack initiation. Test results were compared with ASME design curve and allowable limit of local wall thinning will be discussed.


Nuclear Engineering and Design | 2002

Fracture and general yield for carbon steel pipes with local wall thinning

Katsumasa Miyazaki; Satoshi Kanno; Masayuki Ishiwata; Kunio Hasegawa; Soek Hwan Ahn; Kotoji Ando

Abstract Monotonic bending tests without internal pressure are conducted on 4 and 3.5 in. diameter full-scale carbon steel pipe specimens with local wall thinning in order to evaluate the structural integrity of power plant piping. The local wall thinning is simulated as erosion/corrosion metal loss. The eroded area of the wall thinning is subjected to tensile or compressive stress by applied bending moment. The maximum moments obtained from the tests are compared with the plastic collapse moments based on the net-section stress approach. The net-section stress approach based on flow stress σ f gives a conservative estimation, sometimes overly conservative. Although the net-section approach based on ultimate tensile strength σ u gives a slightly non-conservative estimation for some cases, the calculated values are close to the experimental data. Using the net-section stress approach based on σ u , the eroded depth and the angle at which a pipe undergoes general yielding were obtained.


Nuclear Engineering and Design | 2002

Fracture strength and behavior of carbon steel pipes with local wall thinning subjected to cyclic bending load

Katsumasa Miyazaki; Akira Nebu; Masayuki Ishiwata; Kunio Hasegawa

The power plant piping is designed to withstand seismic events using the design fatigue curve. However, the fatigue strength of a pipe with local wall thinning caused by erosion/corrosion is not clear. To evaluate the fatigue strength of pipes with local wall thinning, low cycle fatigue tests were conducted on 100A carbon steel pipes with local wall thinning. In load controlled tests on these pipes, ratcheting deformation was observed, and the fatigue strength became lower than that of cracked pipes. In displacement controlled tests, the fatigue strength of eroded pipes with 100 mm in eroded axial length, 0.5 in normalized eroded depth and 90° in eroded angle was almost equal to that given by the design fatigue curve in ASME B&PV Code Sec. III. To evaluate the local strain range in the maximum wall thinning area, the finite element analysis was conducted on the eroded pipes in the displacement controlled tests. It is concluded that the Mises strain range in the maximum wall thinning area and the low cycle fatigue curve can be used to conservatively estimate the low cycle fatigue life of an eroded pipe and the validity of estimated results can be confirmed experimentally.


Nuclear Engineering and Design | 1994

Low cycle fatigue and ductile fracture for Japanese carbon steel piping under dynamic loadings

Naoki Miura; Terutaka Fujioka; Koichi Kashima; Satoshi Kanno; Makoto Hayashi; Masayuki Ishiwata; Nobuho Gotoh

Abstract Dynamic fracture behavior of circumferentially cracked pipe is important to evaluate the structural integrity of nuclear piping from the viewpoint of the LBB concept under seismic conditions. Fracture tests have been conducted for Japanese carbon steel (STS410) circumferentially through-wall cracked pipes that are subjected to monotonic or cyclic bending loads at room temperature. In the monotonic-loading tests, the maximum load to failure increases slightly with increasing loading rate. The failure cycles can be expressed simply by ratio of the load amplitude to the plastic collapse load. Fracture analysis has been also conducted to model the pipe tests. A new equation for calculating ΔJ for a circumferentially through-wall cracked pipe subjected to bending has been proposed. The failure cycles under cyclic loads are satisfactorily evaluated using an elastic-plastic fracture mechanics parameter ΔJ .


Nuclear Engineering and Design | 1997

A research program for dynamic fracture evaluation of Japanese carbon steel pipes

Koichi Kashima; Naoki Miura; Satoshi Kanno; Katsumasa Miyazaki; Masayuki Ishiwata; Nobuho Gotoh

A research program was developed to investigate the dynamic load effect on fracture behavior of Japanese carbon steel STS410 pipe. The program comprises material tests, pipe fracture tests and development of estimation scheme. Material property tests showed that the flow stress was nearly constant or slightly increased with strain rate. Pipe tests showed that fracture load was nearly predicted by the net-section collapse criterion for both quasi-static and dynamic loading. Significant dynamic effect was not observed for STS410 carbon steel piping. Crack growth was well formulated by using J-integral parameter for low cycle fatigue with large scale yielding. Combining the crack growth behavior and unstable fracture criterion, an estimation scheme was newly developed and validated for constant amplitude cyclic loading conditions.


Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy | 2006

Application of RFID to High-Reliability Nuclear Power Plant Construction

Kenji Akagi; Masayuki Ishiwata; Kenji Araki; Junichi Kawahata

In nuclear power plant construction, countless variety of parts, products, and jigs more than one million are treated under construction. Furthermore, strict traceability to the history of material, manufacturing, and installation is required for all products from the start to finish of the construction, which enforce much workforce and many costs at every project. In an addition, the operational efficiency improvement is absolutely essential for the effective construction to reduce the initial investment for construction. As one solution, RFID (Radio Frequent Identification) application technology, one of the fundamental technologies to realize a ubiquitous society, currently expands its functionality and general versatility at an accelerating pace in mass-production industry. Hitachi believes RFID technology can be useful of one of the key solutions for the issues in non-mass production industry as well. Under this situation, Hitachi initiated the development of next generation plant concept (ubiquitous plant construction technology) which utilizes information and RFID technologies. In this paper, our application plans of RFID technology to nuclear power is described.Copyright


Journal of The Society of Materials Science, Japan | 1995

Residual-stress measurement in socket welded joints by neutron diffraction

Makoto Hayashi; Masayuki Ishiwata; Noriaki Minakawa; Satoru Funahashi


Journal of The Society of Materials Science, Japan | 2000

Residual Stress Distribution in Carbon Steel Pipe Welded Joint Measured by Neutron Diffraction

Makoto Hayashi; Masayuki Ishiwata; Yukio Morii; Nobuaki Minakawa; J.H. Root


Journal of The Society of Materials Science, Japan | 1995

Diffraction Plane Dependence of Elastic Constants in Ferritic Steel in Neutron Diffraction Stress Measurement.

Makoto Hayashi; Masayuki Ishiwata; Noriaki Minakawa; Satoru Funahashi; John H. Root

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Koichi Kashima

Central Research Institute of Electric Power Industry

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Naoki Miura

Central Research Institute of Electric Power Industry

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Kotoji Ando

Yokohama National University

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Nobuaki Minakawa

Japan Atomic Energy Research Institute

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