Zobrazeno 1 - 10
of 25
pro vyhledávání: '"Takumi Terachi"'
Autor:
Philip J. Withers, Takuyo Yamada, Phani Karamched, Takumi Terachi, Zhao Shen, Koji Arioka, Shengchuan Wu, Naganand Saravanan, Edmund Tarleton, Edward Roberts, David E.J. Armstrong, Sergio Lozano-Perez
The life extension of nuclear power plants beyond 60-years relies on the integrity of the steam generator tubes during the extended life. Alloy 690 steam generator tubes have been generally believed to be resistant to stress corrosion cracking (SCC)
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::a6ce122a9d2947623a0ea79522af98b7
https://ora.ox.ac.uk/objects/uuid:479299a4-49ea-4d71-8d92-e1beb64c9e19
https://ora.ox.ac.uk/objects/uuid:479299a4-49ea-4d71-8d92-e1beb64c9e19
Autor:
Yusa Muroya, Yasuhiko Shoda, Takumi Terachi, Takao Nishimura, Shunsuke Uchida, Hirotaka Kawamura, Yosuke Katsumura, Takayuki Mizuno, Hideo Hirano, Yasuo Tsuzuki, Ryuji Umehara
Publikováno v:
Progress in Nuclear Energy. 114:121-137
In the more than 40 years of operational history of pressurized water reactors (PWRs) in Japan, sustainable development of water chemistry technologies has resulted in the world's highest secondary system component integrity; additionally, secondary
Publikováno v:
Journal of the Atomic Energy Society of Japan. 60:116-119
Autor:
Takumi Terachi, Hirotaka Kawamura, Shunsuke Uchida, Takao Nishimura, Junichi Takagi, Yasuo Tsuzuki, Takayuki Mizuno, Makoto Nagase, Naoshi Usui, Y. Katsumura, Yasuhiko Shoda, Hideaki Kitajima, Hideo Hirano, Hidehiro Urata
Publikováno v:
Nuclear Engineering and Design. 309:161-174
After 40 years of light water reactor (LWR) operations in Japan, the sustainable development of water chemistry technologies has aimed to ensure the highest coolant system component integrity and fuel reliability performance for maintaining LWRs in t
Publikováno v:
The Minerals, Metals & Materials Series ISBN: 9783030046385
The mechanism of primary water stress corrosion cracking (PWSCC) in Alloy TT690 was studied from the viewpoint of the influence of hydrogen behavior and cavity formation. Four parameters were examined: cavity formation at crack tips; deformation in t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::93cfb2f8ebf6902126190ef4fa3da05e
https://doi.org/10.1007/978-3-030-04639-2_7
https://doi.org/10.1007/978-3-030-04639-2_7
Autor:
Takumi Terachi, Kentaro Kajiwara, Koji Arioka, Takuyo Yamada, Masugu Sato, Takuya Fukumura, Tamotsu Hashimoto
Publikováno v:
ISIJ International. 53:165-169
Autor:
Takuyo Yamada, Sergio Lozano-Perez, Karen Kruska, David W. Saxey, Takumi Terachi, George Davey Smith
Atom-probe tomography was employed to characterise specimens containing the oxidised part of a grain boundary from a 304 stainless steel coupon specimen exposed to simulated PWR primary water. A TEM foil containing part of the same oxidised grain bou
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b838e09dbdb271b5ff4c9424bc1487cd
https://doi.org/10.1016/j.corsci.2012.06.030
https://doi.org/10.1016/j.corsci.2012.06.030
Autor:
Takumi Terachi, Koji Arioka, Takuya Fukumura, Takuyo Yamada, Tamotsu Hashimoto, Kentaro Kajiwara, Masugu Sato, Ichiro Hirosawa
Publikováno v:
physica status solidi (a). 206:1838-1841
A visualization method of grain boundaries in a polycrystal was developed at BL28B2 in SPring-8. By combining a scanning type white X-ray micro-diffraction system with high-energy synchrotron X-rays we non-destructively obtained images to visualize g
Publikováno v:
Journal of Nuclear Science and Technology. 45:975-984
Publikováno v:
Journal of Nuclear Science and Technology. 42:225-232
Recent studies on stress corrosion cracking (SCC) behaviors of austenitic stainless steels in hydrogenated high-temperature water show that low potential SCC (LPSCC) can occur on cold-worked SUS 316 stainless steel (hereinafter, 316SS). In this study