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Featured researches published by Yasuhiro Mabuchi.


ASME 2013 Pressure Vessels and Piping Conference | 2013

A Round Robin Program of Master Curve Evaluation Using Miniature C(T) Specimens — 2nd Report: Fracture Toughness Comparison in Specified Loading Rate Condition

Masato Yamamoto; Kunio Onizawa; Kentaro Yoshimoto; Takuya Ogawa; Yasuhiro Mabuchi; Naoki Miura

Master Curve approach for the fracture toughness evaluation is expected to be a powerful tool to ensure the reliability of long term used RPV steels. In order to get sufficient number of data for the Master curve approach coexistent with the present surveillance program for RPVs, the utilization of miniature specimens, which can be taken from broken halves of surveillance Charpy specimens, is important. CRIEPI had developed the test technique for the miniature C(T) specimens (Mini-CT), whose dimensions are 4 × 10 × 10 mm, and verified the basic applicability of the Master Curve approach by means of Mini-CT and larger specimens for the determination of fracture toughness of typical Japanese RPV steels. A round robin program was organized with the participation of a university, industries and a government institute in Japan. The first-round test results (PVP2012-78661[1]) with limited number of reference temperature To data points indicated the possible loading rate dK/dt dependence in To. However, increasing number of data points in second-round test, which was conducted in specified loading rate of 0.5 MPa m0.5 /sec, ensures that there is no clue of such a remarkable dK/dt dependency. Concerning the effect of large plastic deformation on dK/dt, dK/dt calculated by several definitions were compared with each other. Maximum one order difference was found between dK/dts with and without consideration of plastic deformation. dK/dt - T0 relationships showed similar amount of scatter in T0 regardless of dK/dt definitions. Difference in dK/dt definition seems less effective on scatter of T0 in the present results.Copyright


ASME 2014 Pressure Vessels and Piping Conference | 2014

A Round Robin Program of Master Curve Evaluation Using Miniature C(T) Specimens: 3rd Report — Comparison of T0 Under Various Selections of Temperature Conditions

Masato Yamamoto; Akihiko Kimura; Kunio Onizawa; Kentaro Yoshimoto; Takuya Ogawa; Yasuhiro Mabuchi; Hans-Werner Viehrig; Naoki Miura; Naoki Soneda

The Master Curve approach for the fracture toughness evaluation is expected to be a powerful tool to ensure the reliability of long-term used RPV steels. In order to get sufficient number of data for the Master Curve approach coexistent with the present surveillance program for RPVs, the utilization of miniature specimens, which can be taken from broken halves of surveillance Charpy specimens, is important. CRIEPI developed the test technique for the miniature C(T) specimens (Mini-CT), whose dimensions are 4 × 10 × 10 mm, and verified the basic applicability of Master Curve approach by means of Mini-CT for the determination of fracture toughness of typical Japanese RPV steels. A round robin program is organized in order to assure the robustness of the testing procedure to the difference in testing machines or operators. The first and second round robin tests (PVP2012-78661 [1], PVP2013-97936 [2]) suggested that the reference temperature T0 evaluation technique by Mini-CT specimen potentially is fairly robust in regard to difference in testing machines and operators, and gives similar loading rate dependency to the larger C(T) specimens. As the final year of the round robin program, “blind tests” were carried out. Here, detailed material information such as the type of materials, estimated T0, existing fracture toughness data for the material, were not given with the specimen, and 6 organizations independently selected the test temperature based on Charpy full curve of the tested material. The selection of test temperature has the variation of −120 °C to −150 °C among the organizations. 8 to 20 specimens in a set were subjected to the Master Curve evaluation and all the 6 organizations successfully obtained valid T0. The scatter range in T0 was at most 16 °C, which was within the acceptable scatter range specified in ASTM E1921-10e1. The selection of test temperature seems to give limited effect as like as that in larger specimens.Copyright


Archive | 2002

Underwater paint film-repairing method and apparatus

Yasuhiro Mabuchi; Takashiro Matsuo; Makoto Senoo; Masanori Suzuki; Yoshitomo Takahashi; 誠 妹尾; 貴城 松尾; 正憲 鈴木; 靖宏 馬渕; 良知 高橋


Archive | 2012

Natural-circulation boiling water reactor and chimney therefor

Sho Kuroita; Sadakatsu Sawahata; Yasuhiro Mabuchi; Hiroaki Asakura; Fumihito Hirokawa


Archive | 2004

Inspection device for detecting flaw in narrow part

Yasuhiro Mabuchi; Hirokazu Nagaoka; Tsukasa Sasaki; Taiichiro Yamada; 典 佐々木; 泰一郎 山田; 宏和 長岡; 靖宏 馬渕


Archive | 2010

Plant with pipeline having nozzle stub and nuclear power plant with boiling water reactor

Korehisa Fukuda; Hisamichi Inoue; Michiaki Kurosaki; Yasuhiro Mabuchi; Keita Okuyama; Shiro Takahashi; Akinori Tamura; 久道 井上; 圭太 奥山; 明紀 田村; 是寿 福田; 靖宏 馬渕; 志郎 高橋; 通明 黒崎


ASME 2016 Pressure Vessels and Piping Conference | 2016

Defect Tolerance Assessment for ABWR Nozzle Crotch Corner

Fumihito Hirokawa; Masaaki Hayashi; Minoru Masuda; Yasuhiro Mabuchi; Yukinori Yamamoto; Katsumasa Miyazaki; David Johnson


Archive | 2014

International Round Robin Test on Master Curve Reference Temperature Evaluation Utilizing Miniature C(T) Specimen

Masato Yamamoto; Kunio Onizawa; Kentaro Yoshimoto; Takuya Ogawa; Yasuhiro Mabuchi; Matti Valo; Marlies Lambrecht; Hans-Werner Viehrig; Naoki Miura; Naoki Soneda


Journal of Pressure Vessel Technology-transactions of The Asme | 2014

Development of Boiling Water Reactor Steam Dryer Loading Evaluation Methods Through Scale Model Tests Under Actual Steam Conditions

Shiro Takahashi; Keita Okuyama; Akinori Tamura; Yasuhiro Mabuchi; Teppei Kubota; Kazuhiro Yoshikawa


ASME 2013 Pressure Vessels and Piping Conference | 2013

Development of BWR Steam Dryer Loading Evaluation Methods Through Scale Model Tests Under Actual Steam Conditions

Shiro Takahashi; Keita Okuyama; Akinori Tamura; Yasuhiro Mabuchi; Teppei Kubota; Kazuhiro Yoshikawa

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Kentaro Yoshimoto

Mitsubishi Heavy Industries

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Kunio Onizawa

Japan Atomic Energy Agency

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Masato Yamamoto

Central Research Institute of Electric Power Industry

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Naoki Miura

Central Research Institute of Electric Power Industry

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