Zobrazeno 1 - 10
of 285
pro vyhledávání: '"Hiroyasu Tanigawa"'
Autor:
Mitsuru OHATA, Hiroto SHOJI, Kazuma SHIMIZU, Hiroyasu TANIGAWA, Taichiro KATO, Takashi NOZAWA
Publikováno v:
Nihon Kikai Gakkai ronbunshu, Vol 89, Iss 926, Pp 23-00168-23-00168 (2023)
This study aims to develop a numerical simulation-based method for predicting ductile crack growth resistance curve (R-curve) for pre-strained components for rational assessment of ductile crack growth controlling fracture for pre-strained structural
Externí odkaz:
https://doaj.org/article/919a9c34b0f841578d2915d71a75f1b8
Autor:
Hiroshi Sakurai, Kosuke Suzuki, Shoya Ishii, Kazushi Hoshi, Takashi Nozawa, Hidetsugu Ozaki, Hiroto Haga, Hiroyasu Tanigawa, Yoji Someya, Masao Tsuchiya, Hiroshi Takeuchi, Naruki Tsuji
Publikováno v:
Nuclear Materials and Energy, Vol 31, Iss , Pp 101171- (2022)
High energy X-rays (115.56 keV) were used to measure the HIPed interface of F82H steel. The X-ray energy spectra of the samples were analyzed focusing on W and Ta fluorescence X-rays, Compton scattering and elastic scattering X-rays. The results sugg
Externí odkaz:
https://doaj.org/article/f55d5b48c56741ecbec555b10245618d
Autor:
T. Otsuka, S. Masuzaki, N. Ashikawa, Y. Hatano, Y. Asakura, Tatsuya Suzuki, Takumi Suzuki, K. Isobe, T. Hayashi, M. Tokitani, Y. Oya, D. Hamaguchi, H. Kurotaki, R. Sakamoto, Hiroyasu Tanigawa, M. Nakamichi, A. Widdowson, M. Rubel
Publikováno v:
Nuclear Materials and Energy, Vol 17, Iss , Pp 279-283 (2018)
A tritium imaging plate technique (TIPT) in combination with an electron-probe microscopic analysis (EPMA) were applied to examine tritium (T) retention characteristics in individual dust particles collected in the Joint European Torus with the ITER-
Externí odkaz:
https://doaj.org/article/e82863ccfa5d48b08c85d88dfdfe2a4f
Publikováno v:
Nuclear Materials and Energy, Vol 17, Iss , Pp 24-28 (2018)
Micro-tensile tests were conducted on reduced-activation ferritic steel F82H specimens after irradiation with Fe and He ions. The displacement damage levels were 50 and 200 dpa, and helium concentrations were 0, 2000 and 5000 appm. The specimens had
Externí odkaz:
https://doaj.org/article/442a219fc9124cc6b3b134a83e44c589
Instability of MX and M23C6 type precipitates in F82H steels under 2.8 MeV Fe2+ irradiation at 673 K
Autor:
Sho Kano, Huilong Yang, Jingjie Shen, Zishou Zhao, John McGrady, Dai Hamaguchi, Mamami Ando, Hiroyasu Tanigawa, Hiroaki Abe
Publikováno v:
Nuclear Materials and Energy, Vol 17, Iss , Pp 56-61 (2018)
The purpose of this study is to investigate the response of the precipitates against irradiation in F82H steels which are considered as main candidate structure material for the fusion DEMO reactor blanket. M23C6-type precipitates contained F82H-IEA
Externí odkaz:
https://doaj.org/article/d51ed6bc46b44531a690748e9d2c31d5
Publikováno v:
Nihon Kikai Gakkai ronbunshu, Vol 86, Iss 886, Pp 19-00438-19-00438 (2020)
Weibull stress criterion based on the “Local Approach” is applied for rational brittle fracture assessment of steel components taking account of the plastic constraint effect on fracture resistance. Once the cumulative distribution of critical We
Externí odkaz:
https://doaj.org/article/07c24615689e4e12a92a9dc7d7671cd5
Autor:
Hideo Sakasegawa, Xiang Chen, Taichiro Kato, Hiroyasu Tanigawa, Masami Ando, Josina W. Geringer, Shigeharu Ukai, Satoshi Ohtsuka
Publikováno v:
Nuclear Materials and Energy, Vol 16, Iss , Pp 108-113 (2018)
We developed a non-contact deformation measurement system to accurately evaluate strain for post irradiation tensile testing, since conventional strain gages cannot be used for small size specimens. The strain calculated from cross-head displacement
Externí odkaz:
https://doaj.org/article/3e16c63f84984bfc8c3c6c32bd0dde3e
Autor:
Padhraic L. Mulligan, Hideo Sakasegawa, Hiroyasu Tanigawa, Christian M. Petrie, Joel L. McDuffee, Yutai Katoh
Publikováno v:
Nuclear Materials and Energy, Vol 15, Iss , Pp 254-260 (2018)
A novel capsule design has been developed for measurement of irradiation creep in pressurized tubes and is being used to irradiate reduced activation ferritic/martensitic F82H steel creep test specimens. These tests are being conducted in the flux tr
Externí odkaz:
https://doaj.org/article/d0ee5d5129cf4fb5a7958f0f657fa8d4
Autor:
Hisashi Serizawa, Masakazu Murakami, Yoshiaki Morisada, Hidetoshi Fujii, Shuhei Nogami, Takuya Nagasaka, Hiroyasu Tanigawa
Publikováno v:
Nuclear Materials and Energy, Vol 9, Iss C, Pp 367-371 (2016)
As one of the joining methods for the reduced activation materials to realize the fusion reactors with high efficiency in the future, friction stir welding (FSW) is selected for fabricating the dissimilar butt joint between oxide-dispersion strengthe
Externí odkaz:
https://doaj.org/article/894af256c3804e76bf02f200d6e785b3
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