Zobrazeno 1 - 10 of 16 pro vyhledávání: '"Sachio Shimada"'
1
Terminal Solid Solubility of Hydrogen in Hafnium
Autor: Y. Chimi, Katsuhiro Abe, Jin Ogiyanagi, Takehiko Nakamura, Sachio Shimada
Publikováno v: Journal of Nuclear Science and Technology. 47:197-201
The terminal solid solubility (TSS) of hydrogen during hydride dissolution/precipitation is determined by differential scanning calorimetry technique for nonirradiated hafnium (Hf) that is used as control rods of light water reactors. The hydrogen co
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::67d52e1f06473ba28a67513601363fbf
https://doi.org/10.1080/18811248.2010.9711945
Zobrazit plný text záznamu
2
Effect of Hydrogen Water Chemistry on Zircaloy-2 Fuel Cladding and Structure Material Performance
Autor: Yoshiaki Ishii, Sachio Shimada, Shinji Ishimoto, Toshio Matsumoto, Akihiro Miyazaki
Publikováno v: Journal of Nuclear Science and Technology. 43:1021-1030
The effects of hydrogen addition to the feedwater on the corrosion and hydrogen uptake performance of Zircaloy-2 fuel cladding tubes, a water rod tube and spacer materials irradiated for four cycles in a BWR were evaluated. The uniform oxide behavior
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::3e3129fa677e27dab4943c39af73d680
https://doi.org/10.1080/18811248.2006.9711191
Zobrazit plný text záznamu
3
Nuclear Materials and Hydrogen
Autor: Kenji Konashi, Sachio Shimada, Michio Yamawaki
Publikováno v: Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan. 46:457-466
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::52db1f074adce0f38f0f765009bc492b
https://doi.org/10.3327/jaesj.46.457
Zobrazit plný text záznamu
4
A simple model for hydrogen re-distribution in zirconium-lined fuel claddings
Autor: Ikuji Takagi, Sachio Shimada, Kunio Higashi, Daisuke Kawasaki
Publikováno v: Scopus-Elsevier
A simple model of hydrogen diffusion and hydride precipitation was developed to estimate the radial re-distribution of hydrogen in zirconium-lined Zircaloy-2 claddings for light water reactors. Numerical calculation based on the model agreed well wit
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_dedup___::3f8fc87773cb061abebd8e6f3a7ad689
http://hdl.handle.net/2433/7536
Zobrazit plný text záznamu
7
Development of New Zirconium Alloys for a BWR
Autor: Jun Chen, Tadahiro Ikeda, R.B. Adamson, Kazuhiro Takei, Yoshiaki Ishii, Sachio Shimada, Takayoshi Yasuda, Yoshinori Etoh
Specimens for irradiation testing in a commercial BWR were prepared from 24 kinds of Zr alloys. The corrosion performance of these specimens was investigated after irradiation for up to four cycles. Two cycles of irradiation were not always sufficien
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::42689230e9add8c0ec09c70fe95c18f4
https://doi.org/10.1520/stp16203s
Zobrazit plný text záznamu
9
A fractographic study of iodine-induced stress corrosion cracking in irradiated Zircaloy-2 cladding
Autor: Sachio Shimada, Masayuki Nagai
Publikováno v: Journal of Nuclear Materials. 114:222-230
A fractographic interpretation of stress corrosion cracking (SCC) of Zircaloy-2 was made through detailed scanning electron microscope (SEM) examination of cladding tubes irradiated and subjected to internal pressurization SCC tests in an iodine envi
Externí odkaz: https://explore.openaire.eu/search/publication?articleId=doi_________::4cd06c850da9ab2399784ed342df6271
https://doi.org/10.1016/0022-3115(83)90260-x
Zobrazit plný text záznamu

Vyhledávací nástroje:

Upřesnit hledání

Omezení vyhledávání
Plný text Recenzováno Digitální knihovna AV ČR
Zdroje