Zobrazeno 1 - 10
of 97
pro vyhledávání: '"Minoru Narui"'
Publikováno v:
Nuclear Materials and Energy, Vol 9, Iss C, Pp 441-446 (2016)
TEM observation and tensile test were examined for vanadium alloys irradiated in a temperature control rig in JMTR at 290°C with damage level ranged from 0.003 to 0.06dpa. With the increase of the neutron dose, irradiation hardening could be observe
Externí odkaz:
https://doaj.org/article/501a1b91145c4bbf87ea8c5fc57f7b46
Publikováno v:
Nuclear Materials and Energy, Vol 9, Iss C, Pp 441-446 (2016)
TEM observation and tensile test were examined for vanadium alloys irradiated in a temperature control rig in JMTR at 290 °C with damage level ranged from 0.003 to 0.06 dpa. With the increase of the neutron dose, irradiation hardening could be obser
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::1dae084f237e6ceb7e82d88d0d14d6f3
http://www.sciencedirect.com/science/article/pii/S2352179115300612
http://www.sciencedirect.com/science/article/pii/S2352179115300612
Publikováno v:
Journal of Nuclear Materials. 417:295-298
Vanadium alloys, including the highly purified V-4Cr-4Ti alloy, were irradiated in liquid lithium up to a damage level of 3.7 dpa in the HFIR at 425 °C and 598 °C. Neutron irradiation caused an increase of the ductile–brittle transition temperatu
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a92fa82be0540fdea39e7853178616fc
https://doi.org/10.1016/j.jnucmat.2010.12.073
https://doi.org/10.1016/j.jnucmat.2010.12.073
Autor:
Gen Nishijima, Minoru Narui, Arata Nishimura, Tatsuo Shikama, Takao Takeuchi, Kazuo Watanabe, Shigehiro Nishijima, Kentaro Ochiai, Hiroaki Kurishita
Publikováno v:
Journal of Nuclear Materials. 417:842-845
A fusion reactor will yield a lot of high energy neutrons, and some of them will stream out of a plasma vacuum vessel and penetrate a blanket system and reach superconducting magnets which provide high magnetic field to confine high energy ionized pa
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e7131d2ad7835358b679f302c619914d
https://doi.org/10.1016/j.jnucmat.2010.12.148
https://doi.org/10.1016/j.jnucmat.2010.12.148
Publikováno v:
Journal of Nuclear Materials. 417:131-134
The effect of specimen shape on the micro-crack growth behavior of F82H was investigated by the low cycle fatigue test at room temperature in air at the total strain range of 0.4–1.5% using three types of the miniature hourglass-type specimens with
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c872d1098daa7cc3524d19f920d1b278
https://doi.org/10.1016/j.jnucmat.2010.12.048
https://doi.org/10.1016/j.jnucmat.2010.12.048
Publikováno v:
Journal of Nuclear Materials. :594-597
Vanadium alloys, including the highly purified V-4Cr-4Ti alloy called NIFS-Heat2, in the form of sodium-enclosed irradiation capsules, were irradiated up to a damage level of 5 dpa in the Joyo reactor at temperatures from 395 to 601 °C. An increase
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7ae95daac3539ee4e21a1eff213d45b3
https://doi.org/10.1016/j.jnucmat.2008.12.185
https://doi.org/10.1016/j.jnucmat.2008.12.185
Autor:
Takuya Nagasaka, Ken-ichi Fukumoto, Takeo Muroga, Minoru Narui, Steven J. Zinkle, Hideki Matsui, David T. Hoelzer, Meimei Li
Publikováno v:
Journal of Nuclear Materials. :575-578
In order to investigate the effect of the environment on the irradiation creep properties of highly purified V–4Cr–4Ti alloys, neutron irradiation experiments with sodium-enclosed irradiation capsules in Joyo and lithium-enclosed irradiation caps
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4ccb3a34f441c2addd9be52057224324
https://doi.org/10.1016/j.jnucmat.2008.12.180
https://doi.org/10.1016/j.jnucmat.2008.12.180
Autor:
Masanori Yamazaki, Hiroaki Kurishita, H. Arakawa, T. Takida, N. Yoshida, Minoru Narui, K. Takebe, Sengo Kobayashi, Tatsuaki Sakamoto, Masayoshi Kawai, Kiyomichi Nakai, S. Matsuo
Publikováno v:
Journal of Nuclear Materials. :579-582
Ultra-fine grained (UFG) W-TiC consolidates are very promising for use as divertors in fusion reactors, however, the assurance of room-temperature ductility of UFG W-TiC remains unsettled. The assurance requires a sufficient degree of plastic working
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::424808f42f3818dcd2d64ddead1d3822
https://doi.org/10.1016/j.jnucmat.2008.12.181
https://doi.org/10.1016/j.jnucmat.2008.12.181
Publikováno v:
Journal of Nuclear Science and Technology. 45:171-178
In order to perform irradiation experiments in a liquid metal environment in a nuclear reactor, an irradiation technique with sodium bonding irradiation capsules was developed and a series of neutron irradiation experiments with sodium bonding irradi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b2435c19cc539a0cec6e1aa81d9953e3
https://doi.org/10.1080/18811248.2008.9711426
https://doi.org/10.1080/18811248.2008.9711426
Radiation enhanced diffusion of hydrogen in perovskite-type oxide ceramics under reactor irradiation
Publikováno v:
Journal of Nuclear Materials. :1073-1078
Electrical conductivity of yttrium-doped perovskite-type barium-cerium oxide ceramics (BaCe 0.9 Y 0.1 O 3-δ ), implanted with 10 keV H 2 + ions, was measured in situ under fission reactor irradiation. An increment of the electrical conductivity, cal
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::54040a1cfa88378a5f5017c49a52e33d
https://doi.org/10.1016/j.jnucmat.2007.03.200
https://doi.org/10.1016/j.jnucmat.2007.03.200