Zobrazeno 1 - 10
of 147
pro vyhledávání: '"Mikio Enoeda"'
Autor:
Koichiro Ezato, M. Tokitani, T. Hotta, Suguru Masuzaki, Masato Akiba, Mikio Enoeda, Akira Kurumada, Katsumasa Nakamura, S. Suzuki, Kazutoshi Tokunaga, K. Araki, Makoto Hasegawa
Publikováno v:
Fusion Engineering and Design. 136:1624-1628
Tungsten coating with a thickness of 1 mm on reduced-activation ferritic/martensitic steel (RAF/M) F82H (Fe-8Cr-2W), which is a leading structural material candidate for DEMO, have been produced by Atmospheric Plasma Spraying (APS) and Vacuum Plasma
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2203afe7613020181c4dad9a31e081b4
https://doi.org/10.1016/j.fusengdes.2018.05.073
https://doi.org/10.1016/j.fusengdes.2018.05.073
Autor:
Yuki Edao, Tsuyoshi Hoshino, Hiroyasu Tanigawa, Toshihiko Yamanishi, Satoshi Suzuki, Kentaro Ochiai, Mikio Enoeda, Yohji Seki, Satoshi Sato, Koichiro Ezato, Hiroshi Nishi, Chikara Konno, Hisashi Tanigawa, Takanori Hirose, Takumi Hayashi, Yoshinori Kawamura, Masaru Nakamichi
Publikováno v:
Fusion Engineering and Design. :1637-1643
The development of a water cooled ceramic breeder (WCCB) test blanket module (TBM) is being performed as one of the most important steps toward DEMO blanket in Japan. For the TBM testing and development of DEMO blanket, R&D has been performed on the
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d0ae2065636021c9369ae9e0eb01135f
https://doi.org/10.1016/j.fusengdes.2015.11.002
https://doi.org/10.1016/j.fusengdes.2015.11.002
Publikováno v:
Fusion Engineering and Design. :1864-1867
A water cooled ceramic breeder for ITER and DEMO of a nuclear fusion reactor plays a significant role in the design of a blanket module. Pebbles of a ceramic tritium breeder are packed in a container of the blanket. Investigation of the flow behavior
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b42b632c074afafab137088ecf15973c
https://doi.org/10.1016/j.fusengdes.2015.03.023
https://doi.org/10.1016/j.fusengdes.2015.03.023
Autor:
Satoshi Konishi, Motoki Nakajima, Hiroyasu Tanigawa, Takanori Hirose, Mikio Enoeda, A. Kanai, Ryuta Kasada
Publikováno v:
Journal of Nuclear Materials. 455:431-435
The present study reports the corrosion behavior of a reduced-activation ferritic martensitic steel F82H exposed to high temperature pressurized water for 28 and 100 h using a rotating disk apparatus at rotation speeds of 500 and 1000 rpm at a temper
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::849bee635151ce5281f8102a2f4d8753
https://doi.org/10.1016/j.jnucmat.2014.07.067
https://doi.org/10.1016/j.jnucmat.2014.07.067
Autor:
Kentaro Ochiai, Koichiro Ezato, Satoshi Suzuki, Takanori Hirose, Chikara Konno, Mikio Enoeda, Yohji Seki, Yoshinori Kawamura, Hisashi Tanigawa, Masaru Nakamichi, Hiroyasu Tanigawa, Motoki Nakajima, Toshihiko Yamanishi, Kenji Yokoyama, Tsuyoshi Hoshino, Satoshi Sato, Hiroshi Nishi, Takumi Hayashi
Publikováno v:
Fusion Engineering and Design. 89:1131-1136
Japan Atomic Energy Agency (JAEA) is performing the development of a Water Cooled Ceramic Breeder (WCCB) Test Blanket Module (TBM) as one of the most important steps toward DEMO blanket. Regarding the blanket module fabrication technology development
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::76120451fc893ce5ae36bc2e0373028c
https://doi.org/10.1016/j.fusengdes.2014.01.035
https://doi.org/10.1016/j.fusengdes.2014.01.035
Publikováno v:
Fusion Engineering and Design. 89:1280-1283
Lithium titanate (Li2TiO3) pebbles were irradiated with D3+ ions with energy of 5.0 keV, and the amounts of retained deuterium in the pebbles were measured by thermal desorption spectroscopy. In this research the irradiation/heating cycles were carri
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ae5bbf75323d18a5cd44e37ae5ce45ef
https://doi.org/10.1016/j.fusengdes.2014.03.054
https://doi.org/10.1016/j.fusengdes.2014.03.054
Publikováno v:
Fusion Engineering and Design. 89:1984-1988
To evaluate the nuclear properties of the International Thermonuclear Experimental Reactor (ITER) JA Water-Cooled Ceramic Breeder Test Blanket Module (WCCB-TBM) and to ensure its design conforms to nuclear licensing regulations, nuclear analyses have
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ccb7a99c03f2368601bdbceb53e30c0a
https://doi.org/10.1016/j.fusengdes.2013.12.015
https://doi.org/10.1016/j.fusengdes.2013.12.015
Autor:
Lance Lewis Snead, Hiroyasu Tanigawa, Roger E. Stoller, Yutai Katoh, Takashi Nozawa, Dai Hamaguchi, Hideo Sakasegawa, Mikio Enoeda, Takanori Hirose, Hisashi Tanigawa
Publikováno v:
Fusion Engineering and Design. 89:1595-1599
The material properties, focusing on the properties used for design analysis were re-assessed and newly investigated for various heats of reduced activation ferritic/martensitic steel, F82H. Moreover, irradiation effects on those properties were stud
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e583f137757bfd57ff5dfbddff8272cd
https://doi.org/10.1016/j.fusengdes.2013.12.005
https://doi.org/10.1016/j.fusengdes.2013.12.005
Autor:
Kenichi Hashizume, Sadaaki Suzuki, Koichiro Ezato, Teppei Otsuka, Masato Akiba, Kazutoshi Tokunaga, Mikio Enoeda, M. Higaki
Publikováno v:
Fusion Science and Technology. 67:379-381
Hydrogen diffusion coefficients in a reduced activation ferritic/martensitic steel (F82H) and an oxide dispersion strengthened F82H (ODS-F82H) have been determined from depth profiles of plasma-loa...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8a1597df8db0453c5767e8b85f63bbaf
https://doi.org/10.13182/fst14-t33
https://doi.org/10.13182/fst14-t33
Autor:
Sadaaki Suzuki, K. Araki, Kazutoshi Tokunaga, Mikio Enoeda, Y. Miyamoto, Koichiro Ezato, Katsumasa Nakamura, Makoto Hasegawa, Takuya Nagasaka, T. Fujiwara, Ryuta Kasada, Masato Akiba, Akihiko Kimura, T. Hotta
Publikováno v:
Journal of Nuclear Materials. 438:S905-S908
High density W coatings on reduced activation ferritic martensitic steel (RAF/M) have been produced by Vacuum Plasma Spraying technique (VPS) and heat flux experiments on them have been carried out to evaluate their possibility as a plasma-facing arm
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::73de427a497c5df7cc4f5e645673dbd7
https://doi.org/10.1016/j.jnucmat.2013.01.196
https://doi.org/10.1016/j.jnucmat.2013.01.196