Zobrazeno 1 - 10
of 12
pro vyhledávání: '"Yen-Jui Huang"'
Publikováno v:
Nuclear Materials and Energy, Vol 31, Iss , Pp 101190- (2022)
In Japan Demonstration fusion reactor, the divertor plays a critical role for it helps sustaining plasma shape and hence demanding high requirements on its structural materials for the cooling system. CuCrZr alloy is considered as one of candidates a
Externí odkaz:
https://doaj.org/article/d481650a5be54ac697489e4a86a3fd40
Publikováno v:
Nuclear Materials and Energy, Vol 15, Iss , Pp 103-109 (2018)
The stress corrosion cracking (SCC) susceptibility of solution-annealed 310S stainless steel (SS) was examined by means of slow-strain rate test (SSRT) method in hot water (288 °C) with dissolved-hydrogen (DH), and the results were compared with tho
Externí odkaz:
https://doaj.org/article/681213aa02464341aa320de41e6e3103
Autor:
Yen-jui Huang, 黃彥叡
96
Ancestral Estates will become a right master after conducting “Statute For Ancestral Estates In Joint Ownership”. But its states of be a right master will be different from legal foundation and corporation juridical person. There will be
Ancestral Estates will become a right master after conducting “Statute For Ancestral Estates In Joint Ownership”. But its states of be a right master will be different from legal foundation and corporation juridical person. There will be
Externí odkaz:
http://ndltd.ncl.edu.tw/handle/80975916877136866321
Autor:
Kiyohiro Yabuuchi, Yen-Jui Huang, Akihiko Kimura, Kan Sakamoto, Shinichiro Yamashita, Jin Gao, Peng Song
Publikováno v:
Journal of Nuclear Materials. 524:1-8
Oxide dispersion strengthened (ODS) steels have been developed as accident tolerant fuel cladding materials because of their excellent high temperature oxidation resistance as well as high temperature mechanical properties. 12Cr–6Al-ODS steel speci
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::01a0373c205c50049a2299300f1c97c1
https://doi.org/10.1016/j.jnucmat.2019.06.028
https://doi.org/10.1016/j.jnucmat.2019.06.028
Autor:
Akihiko Kimura, Takahiro Yamaguchi, Kousuke Kawakita, Hirotoshi Murai, Yen-Jui Huang, Hiroki Sugino, Masahiro Nono, Tetsuya Nakajima
Publikováno v:
Corrosion Science. 145:1-9
Stress corrosion cracking (SCC) susceptibility of solution-annealed 316L stainless steel was evaluated by slow strain rate test in oxygenated, deaerated and hydrogenated water below 288 °C. At 288 °C, no SCC was found in the specimens tested in oxy
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9fa6a62b497205898eb4cb8fc110da1f
https://doi.org/10.1016/j.corsci.2018.09.005
https://doi.org/10.1016/j.corsci.2018.09.005
Autor:
Akihiko Kimura, Yen-Jui Huang
Publikováno v:
MATERIALS TRANSACTIONS. 59:1267-1274
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9a73aacdaa361fd432936641290d9ddd
https://doi.org/10.2320/matertrans.m2018064
https://doi.org/10.2320/matertrans.m2018064
Publikováno v:
Nuclear Materials and Energy, Vol 15, Iss, Pp 103-109 (2018)
The stress corrosion cracking (SCC) susceptibility of solution-annealed 310S stainless steel (SS) was examined by means of slow-strain rate test (SSRT) method in hot water (288 °C) with dissolved-hydrogen (DH), and the results were compared with tho
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::9408a53322aeabea7fb423f84d5c3f98
http://hdl.handle.net/2433/233812
http://hdl.handle.net/2433/233812
Autor:
Ryuta Kasada, Zhexian Zhang, Yen-Jui Huang, Kiyohiro Yabuuchi, Eva Hasenhuetl, Akihiko Kimura
Publikováno v:
MATERIALS TRANSACTIONS. 58:749-756
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::85ba5fc2572f754b28b742fe5281b048
https://doi.org/10.2320/matertrans.m2016437
https://doi.org/10.2320/matertrans.m2016437
Autor:
Peng Song, Kiyohiro Yabuuchi, Jin Gao, Peng Dou, Akihiko Kimura, Yen-Jui Huang, Hideo Watanabe
Publikováno v:
Journal of Nuclear Materials. 529:151953
Three types of 15Cr-ODS ferritic steels were irradiated with 6.4 MeV Fe3+ at 200 °C up to a nominal displacement damage of 10 dpa to assess the phase stability of different sorts of oxide particles under ion-irradiation. Before the irradiation, domi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::11ba5d3e88db4c1542dc3982517b77bb
https://doi.org/10.1016/j.jnucmat.2019.151953
https://doi.org/10.1016/j.jnucmat.2019.151953
Autor:
Shinichiro Yamashita, Jin Gao, Kiyohiro Yabuuchi, Akihiko Kimura, Kan Sakamoto, Yen-Jui Huang, Peng Song, Yuuki Yamasaki
Publikováno v:
Journal of Nuclear Materials. 528:151858
Oxide dispersion strengthened (ODS) steels are promising accident tolerant fuel (ATF) cladding alternatives because of their excellent oxidation resistance and mechanical properties at high temperatures. Coupons of 12Cr–6Al-ODS steel with an electr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::33f6e86abd753137f7363380e79f7174
https://doi.org/10.1016/j.jnucmat.2019.151858
https://doi.org/10.1016/j.jnucmat.2019.151858