Zobrazeno 1 - 6
of 6
pro vyhledávání: '"Takashi Sakamura"'
Publikováno v:
Journal of the Surface Finishing Society of Japan. 67:662-666
Autor:
Takashi Sakamura, Satoshi Ohtsuka, Takeji Kaito, Wataru Izawa, Naoko Oono, Shigeharu Ukai, Yutaka Kohno, Shigenari Hayashi
Publikováno v:
PRICM: 8 Pacific Rim International Congress on Advanced Materials and Processing
The oxide dispersion strengthened (ODS) ferritic steels are expected as the structural materials for the advanced fusion reactors due to superior radiation resistance and high-temperature strength. Mechanically alloyed powders were consolidated by ho
Autor:
Yutaka Kohno, Tetsuya Honda, Kota Sawada, Takashi Sakamura, Kazuhiro Kimura, Shin-ichi Komazaki
Publikováno v:
Tetsu-to-Hagane. 96:614-619
Hydrogen is usually trapped by vacancy, dislocation, grain boundary, precipitate and void in steels and it is easily released from these trap sites by heating the steels. However, the desorption temperature ranges vary according to the kinds of trap
Publikováno v:
Journal of Nuclear Materials. 417:33-35
It is well known that diffusible hydrogen in steels causes the reduction of fracture strength of steels. The hydrogen is usually trapped by vacancies, dislocations, grain boundaries, precipitates, voids, etc. The trapped hydrogen is thermally release
Autor:
Takuya Nagasaka, Masao Matsuyama, Takeo Muroga, Hirofumi Homma, Hideyuki Saitoh, Yuji Hatano, Takashi Sakamura
Publikováno v:
Journal of Nuclear Materials. :569-571
Distribution of hydrogen isotopes was examined by tritium radioluminography using imaging plates for specimens of a V–4Cr–4Ti alloy prepared from two different plates fabricated with cold rolling under two different conditions (93% and 96% reduct
Autor:
Satoshi Ohtsuka, Takashi Sakamura, Shigeharu Ukai, Wataru Izawa, Naoko Oono, Yutaka Kohno, Shigenari Hayashi, Takeji Kaito
Publikováno v:
Proceedings of the 8th Pacific Rim International Congress on Advanced Materials and Processing ISBN: 9783319485867
The oxide dispersion strengthened (ODS) ferritic steels are expected as the structural materials for the advanced fusion reactors due to superior radiation resistance and high-temperature strength. Mechanically alloyed powders were consolidated by ho
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::04cc5d64fc94b3240e07832cb2b81f45
https://doi.org/10.1007/978-3-319-48764-9_15
https://doi.org/10.1007/978-3-319-48764-9_15