Zobrazeno 1 - 10
of 248
pro vyhledávání: '"Masabumi, Nishikawa"'
Autor:
Satoshi Fukada, Masabumi Nishikawa, Hiroki Ushida, Kazunari Katayama, Shohei Matsuda, Motoki Shimozori
Publikováno v:
Fusion Science and Technology. 67:467-470
F82H is a primary candidate of structural material and coolant pipe material in a blanket of a fusion reactor. Understanding tritium permeation behavior through F82H is important. In a normal operation of a fusion reactor, the temperature of F82H wil
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7e0bf736b47297d6b8ecf3999dc98bc6
https://doi.org/10.13182/fst14-t56
https://doi.org/10.13182/fst14-t56
Autor:
Satoshi Akamaru, T. Tanabe, Yuji Hatano, Masabumi Nishikawa, K. Ogata, Kenichi Hashizume, S. Abe
Publikováno v:
Journal of Nuclear Materials. 442:S880-S884
Using a tritium imaging plate technique, kinetics of tritium dissolution and its solubility in several oxides were examined. Mirror-polished single crystals of alumina, spinel and zirconia were used as specimens, which were exposed to 133 Pa of a tri
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b769df1274e30d1dbfd253bf1249f9b0
https://doi.org/10.1016/j.jnucmat.2013.05.038
https://doi.org/10.1016/j.jnucmat.2013.05.038
Autor:
Masabumi Nishikawa, Hideaki Kashimura, Satoshi Fukada, Kazunari Katayama, Toshiharu Takeishi, Shohei Matsuda, Tsuyoshi Hoshino
Publikováno v:
Fusion Engineering and Design. 88:2400-2403
Tritium sorption capacity is an important parameter to evaluate tritium behavior on lithium ceramic breeder materials. In the present study, sorption and desorption behavior of tritiated water on Li2TiO3 with additional Li, which is in a developmenta
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a2e52e7f1757a4b0ff998b66ba129c28
https://doi.org/10.1016/j.fusengdes.2013.05.041
https://doi.org/10.1016/j.fusengdes.2013.05.041
Autor:
Satoshi Fukada, Kazunari Katayama, Hideaki Kashimura, Motoki Shimozori, Shohei Matsuda, Tsuyoshi Hoshino, Masabumi Nishikawa
Publikováno v:
Fusion Engineering and Design. 88:2202-2205
It has been known that water vapor is released from ceramic breeder materials into the purge gas due to desorption of adsorbed water under dry atmosphere and due to the water formation reaction under hydrogen atmosphere. However, an effect of water v
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1a62186c1729e35cd5d2281649c9fd4c
https://doi.org/10.1016/j.fusengdes.2013.05.098
https://doi.org/10.1016/j.fusengdes.2013.05.098
Autor:
Hideaki Matsuura, Minoru Goto, Masabumi Nishikawa, Yasuyuki Nakao, Hiroyuki Nakaya, Satoshi Shimakawa, Shigeaki Nakagawa
Publikováno v:
Fusion Engineering and Design. 88:2219-2222
The performance of a high-temperature gas-cooled reactor as a tritium production with continuous tritium recovery system is examined. A gas turbine high-temperature reactor of 300-MWe (600 MW) nominal capacity (GTHTR300) is assumed as the calculation
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::932b53e2b037981a42ad82985c254747
https://doi.org/10.1016/j.fusengdes.2013.05.022
https://doi.org/10.1016/j.fusengdes.2013.05.022
Autor:
Kazunari Katayama, Masabumi Nishikawa, Satoshi Fukada, Naoko Ashikawa, T. Honda, Tatsuhiko Uda, Yasuhito Ohnishi, Keiichiro Uehara
Publikováno v:
Journal of Nuclear Materials. 438:S1010-S1013
The influence of the deposition conditions on hydrogen incorporation into metal deposits was investigated by exposing tungsten (W) or stainless steel (SS) to mixed hydrogen and argon plasma. The sputtering yield of SS was lower than expected from a s
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b5c1d09995685847c58c3fc6ab51cec3
https://doi.org/10.1016/j.jnucmat.2013.01.220
https://doi.org/10.1016/j.jnucmat.2013.01.220
Autor:
Kazunari Katayama, Masabumi Nishikawa
Publikováno v:
Tritium: Fuel of Fusion Reactors ISBN: 9784431564584
In order to ensure tritium (T) fuel self-sufficiency in a fusion power plant, key issues are full recovery of T generated in breeder materials and minimization of T loss in all fuel cycle systems. To realize the full recovery, T behavior in the breed
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::54df2e6583fd4cec60786cd58f68414f
https://doi.org/10.1007/978-4-431-56460-7_13
https://doi.org/10.1007/978-4-431-56460-7_13
Autor:
Kazunari Katayama, Masabumi Nishikawa
Publikováno v:
Tritium: Fuel of Fusion Reactors ISBN: 9784431564584
A large amount of T is used as a fuel in a fusion reactor, but its release to the environment is rigidly regulated to be quite low by law. In order to protect workers , the public, and the environment from radiation of T, it is very important to conf
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::611cb2a5d101400960f97445a0145aa0
https://doi.org/10.1007/978-4-431-56460-7_14
https://doi.org/10.1007/978-4-431-56460-7_14
Autor:
Hideaki Matsuura, Masabumi Nishikawa
Publikováno v:
Tritium: Fuel of Fusion Reactors ISBN: 9784431564584
The breeding blanket is the only place to produce tritium (T) in a fusion reactor. It is necessary to recover bred T in the blanket effectively because no T in the natural resources is usable as the fuel in a fusion reactor . Fortunately, T can be pr
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9e2b9fe18be2195c37c766e94cd8a381
https://doi.org/10.1007/978-4-431-56460-7_12
https://doi.org/10.1007/978-4-431-56460-7_12
Autor:
Masabumi Nishikawa, Tetsuo Tanabe
Publikováno v:
Tritium: Fuel of Fusion Reactors ISBN: 9784431564584
Because of radioactivity of tritium (T), special cares for safety are required. In addition, limited resources of T require fuel self-sufficiency in a fusion reactor. Accordingly, accurate T accountancy, i.e., to know quantitatively how much T is in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::22d47e7465e67b3a632b56e434c82965
https://doi.org/10.1007/978-4-431-56460-7_3
https://doi.org/10.1007/978-4-431-56460-7_3