Zobrazeno 1 - 10
of 52
pro vyhledávání: '"Norikazu Yamamoto"'
Publikováno v:
MATERIALS TRANSACTIONS. 58:1386-1391
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c805d1682efc4000adc651466642d3de
https://doi.org/10.2320/matertrans.maw201701
https://doi.org/10.2320/matertrans.maw201701
Publikováno v:
MATERIALS TRANSACTIONS. 56:570-575
Stress corrosion tests were performed for welded 308 stainless steel under proton irradiation at 473K in aerated water (DO: 0.150.22ppm, DH
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::099e8fa581123337f34fcd48eb33ec7f
https://doi.org/10.2320/matertrans.mbw201404
https://doi.org/10.2320/matertrans.mbw201404
Autor:
Yoshiharu Murase, Norikazu Yamamoto
Publikováno v:
Journal of Nuclear Materials. 442:S730-S734
Stress-controlled fatigue tests were performed for He-pre-injected 316 stainless steels under in situ 17 MeV proton irradiation at 573 K. The pre-injection of He for fatigue specimens was conducted with 20 MeV α particles to a level of 100 appm at 5
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a08d2fabe9b3e09c2f48378eeb530b9a
https://doi.org/10.1016/j.jnucmat.2013.03.064
https://doi.org/10.1016/j.jnucmat.2013.03.064
Publikováno v:
Journal of Nuclear Materials. 417:120-123
In situ stress-controlled fatigue tests were performed for F82H steels under 17 MeV proton irradiation with an energy degrader at 60 °C. The energy degrader enhanced the hydrogen implantation rate from 2.6 × 10 −6 to 1.3 × 10 −3 appm/s at a do
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::89dd29d52c621cae54a85bb2389ae3f6
https://doi.org/10.1016/j.jnucmat.2010.12.049
https://doi.org/10.1016/j.jnucmat.2010.12.049
Publikováno v:
Solid State Ionics. 185:52-57
Ni cermet anodes were prepared from nanoparticle solid solutions of Y 2 O 3 ―CeO 2 ―ZrO 2 with various CeO 2 contents, (Y 2 O 3 ) 0.08 (CeO 2 ) x (ZrO 2 ) 0.92-x (x = 0–0.08). The performance of cells with anodes prepared from solid solutions w
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::56b5435a68b0abe09c68d5fcdeb1e1ff
https://doi.org/10.1016/j.ssi.2011.01.003
https://doi.org/10.1016/j.ssi.2011.01.003
Autor:
Yoshiharu Murase, Norikazu Yamamoto
Publikováno v:
MATERIALS TRANSACTIONS. 52:423-427
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2a05e17510500c5c1fdb219059abc49f
https://doi.org/10.2320/matertrans.mbw201014
https://doi.org/10.2320/matertrans.mbw201014
Publikováno v:
Journal of Nuclear Materials. :264-267
Although fusion blankets are exposed to severe irradiation, its rear side would stay at rather a modest condition. In this research, the irradiation-induced deformation of F82H IEA-heat steel at 300 °C was examined. A torsion creep apparatus with a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c1bb6cac4d5c55a9e3941a4c9beee76f
https://doi.org/10.1016/j.jnucmat.2008.12.108
https://doi.org/10.1016/j.jnucmat.2008.12.108
Publikováno v:
MATERIALS TRANSACTIONS. 50:740-743
In order to contribute to the development of first wall/blanket structural materials in nuclear fusion reactors, we have assessed the influence of nuclear-transmutational helium, which is widely known to often induce grain boundary embrittlement at h
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::68c0074c58ffebbd53e87c9dd5534bcf
https://doi.org/10.2320/matertrans.mbw200811
https://doi.org/10.2320/matertrans.mbw200811
Publikováno v:
MATERIALS TRANSACTIONS. 49:2243-2246
Stress-controlled fatigue tests were performed for 5% and 15% cold-worked 304 stainless steels under in-situ irradiation with 17 MeV protons at 300°C. Increase of fatigue life with prolonged crack propagation length under in-situ irradiation was det
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fd804e4ae230af48f472e5da0b9e8f6e
https://doi.org/10.2320/matertrans.maw200806
https://doi.org/10.2320/matertrans.maw200806
Publikováno v:
Journal of Nuclear Materials. :910-914
Austenitic stainless steels will be used in ITER as a major structural material. Although, initially supplied in annealed condition, cold-working is inevitable during construction or operation. Martensite would be introduced by cold-work in the case
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a2fd78085a3fbcaa45c00af1314baf4f
https://doi.org/10.1016/j.jnucmat.2007.03.063
https://doi.org/10.1016/j.jnucmat.2007.03.063