Zobrazeno 1 - 10
of 31
pro vyhledávání: '"Hideki Takiguchi"'
Autor:
Yasushi Uehara, Shunsuke Uchida, Taku Ohira, Hideki Takiguchi, Masanori Naitoh, Hidetoshi Okada, Seiichi Koshizuka, Wataru Sugino
Publikováno v:
Journal of Nuclear Science and Technology. 47:184-196
In order to confirm applicability and accuracy of FAC evaluation methods based on the coupled FAC model of static electrochemical analysis and dynamic oxide layer growth analysis, wall thinning rates calculated with the proposed methods were compared
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1ff3d408cd7ce47817612ad6a7f6facf
https://doi.org/10.1080/18811248.2010.9711944
https://doi.org/10.1080/18811248.2010.9711944
Autor:
Yoshinori Matsui, Yoshiyuki Kaji, Junichi Nakano, Akira Shibata, Takashi Tsukada, Koji Dozaki, Masao Ohmi, Kazuo Kawamata, Hirokazu Ugachi, Nobuaki Nagata, Hideki Takiguchi
Publikováno v:
Journal of Nuclear Science and Technology. 45:725-734
Irradiation-assisted stress corrosion cracking (IASCC) is one of the critical concerns when stainless steel components have been in service in light water reactors for a long period. In-core IASCC growth tests have been carried out using the compact
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::afdf3f5ff77c47011d21d1ca5d55366c
https://doi.org/10.1080/18811248.2008.9711473
https://doi.org/10.1080/18811248.2008.9711473
Publikováno v:
Journal of the Atomic Energy Society of Japan. 50:506-510
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::095ccbd1be3a879c800b7f314afbeae8
https://doi.org/10.3327/jaesjb.50.8_506
https://doi.org/10.3327/jaesjb.50.8_506
Autor:
Kazushige Ishida, Eiichi Kadoi, Motomasa Fuse, Hideki Takiguchi, Yoichi Wada, Motohiro Aizawa, Masahiko Tachibana
Publikováno v:
Journal of Nuclear Science and Technology. 44:1550-1556
Hydrogen and hydrazine co-injection into a boiling water reactor was considered as a new mitigation method of stress corrosion cracking (SCC). In this method, some amount of ammonia will be formed by the decomposition of hydrazine. The effect of ammo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::55eedcb38813d0d343f5697201ada74b
https://doi.org/10.1080/18811248.2007.9711405
https://doi.org/10.1080/18811248.2007.9711405
Autor:
Motomasa Fuse, Yoichi Wada, Masahiko Tachibana, Nobuaki Nagata, Hideki Takiguchi, Masato Nakamura
Publikováno v:
Transactions of the Atomic Energy Society of Japan. 6:183-195
We studied the effect of the flow rate of reactor water on crack growth rates (CGRs) in a boiling water reactor (BWR) coolant system using 1/4TCT specimens made of sensitized 304 stainless steel (SUS304). Specimen electrochemical corrosion potentials
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::20c87de87d61e4a9a61362d00d1d3d38
https://doi.org/10.3327/taesj.j06.022
https://doi.org/10.3327/taesj.j06.022
Autor:
Hideo Hirano, Kazutoshi Fujiwara, Shuuichi Yamamoto, Hiromi Kanbe, Hideki Takiguchi, Kenkichi Ishigure, Toshio Shibata, Hirotaka Kawamura, Kouji Yoshino
Publikováno v:
Journal of Nuclear Science and Technology. 43:1344-1358
The application of chemical cleaning for dissolving and removing scale and sludge is being planned in the Japanese pressurized water reactor (PWR) plant in order to maintain high heat transfer performance and to prevent steam generator (SG) tube degr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c2a06e8e2b8afda14c0651a488a68a5c
https://doi.org/10.1080/18811248.2006.9711229
https://doi.org/10.1080/18811248.2006.9711229
Autor:
Yoichi Wada, Masahiko Tachibana, Eiichi Kadoi, Motohiro Aizawa, Kazushige Ishida, Motomasa Fuse, Hideki Takiguchi
Publikováno v:
Journal of Nuclear Science and Technology. 43:242-254
Hydrogen and hydrazine co-injection into a boiling water reactor was considered as a new mitigation method of stress corrosion cracking. To confirm decrease of electrochemical corrosion potential by the reduction of oxygen and hydrogen peroxide in bu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::42ff6bd6a58c3bbf8b07bfa25e2ba11a
https://doi.org/10.1080/18811248.2006.9711086
https://doi.org/10.1080/18811248.2006.9711086
Autor:
Hideo Hirano, Kazutoshi Fujiwara, Shuuichi Yamamoto, Kouji Yoshino, Toshio Shibata, Kenkichi Ishigure, Hideki Takiguchi, Hirotaka Kawamura, Hiromi Kanbe
Publikováno v:
Journal of Nuclear Science and Technology. 42:275-288
The application of a chemical cleaning process to dissolve and remove scale and sludge by chemicals is being planned for Japanese pressurized water reactor (PWR) plants in order to maintain a high heat transfer condition and to prevent the SG tubing
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::119983e6d5da943aedd1ee0d643a6e1e
https://doi.org/10.1080/18811248.2005.9726391
https://doi.org/10.1080/18811248.2005.9726391
Publikováno v:
Nuclear Science and Engineering. 149:312-324
Hydrogen injection has been applied as a preventive measure against the stress corrosion cracking (SCC) phenomenon in many boiling water reactors. However, it can be applied only during normal plant operation since hydrogen is usually injected into t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2b138c0f04e031913b1ecffe44463bfb
https://doi.org/10.13182/nse149-312
https://doi.org/10.13182/nse149-312
Publikováno v:
Journal of Nuclear Science and Technology. 41:601-609
Optimization of the dissolved hydrogen concentration in primary coolant of pressurized water reactors has several potential advantages in material integrity and dose reduction. To assess the threshold value of dissolved hydrogen for reducing conditio
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b2409f547070da00723076a76858277c
https://doi.org/10.1080/18811248.2004.9715523
https://doi.org/10.1080/18811248.2004.9715523