Zobrazeno 1 - 6
of 6
pro vyhledávání: '"Masato Akiba"'
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
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...
Autor:
Yuji Hatano, Yuji Yamauchi, Tomoaki Hino, S. Suzuki, Masao Matsuyama, Y. Nobutaa, Masato Akiba, Satoshi Akamaru
Publikováno v:
Fusion Science and Technology. 60:1535-1538
Tritium retention in plasma facing materials is a primary issue for ITER and next step fusion devices, since it greatly affects its safety and operational schedule. In the ITER, carbon and tungsten...
Publikováno v:
Fusion Science and Technology. 41:943-947
Tritium retention of carbon dust co-deposited with fuel hydrogen is large, and then it is required to evaluate the tritium inventory as a safety issue of ITER. Several species of co-deposited carbon dust were prepared by D 2 arc discharge with carbon
Autor:
Satoshi Suzuki, M. Dairaku, Masanori Araki, K. Yokoyama, Kazuyuki Nakamura, Masato Akiba, Kazuyoshi Sato
Publikováno v:
Fusion Technology. 30:769-773
CVD-tungsten coated divertor mock-ups were fabricated and tested in an ion beam test facility in JAERI. The mock-up consisted of a 2 mm thick CVD-tungsten on a 30 wt% Cu infiltrated tungsten skeleton heat sink. For the thermal fatigue tests, the heat
Autor:
Mikio Enoeda, Masato Akiba, Takeo Nishitani, Hiroyasu Tanigawa, Toshihiko Yamanishi, K. Hayashi
Publikováno v:
Scopus-Elsevier
Japan Atomic Energy Agency (JAEA) plays a role of the principal institute in Japan for the design and the development of a solid breeder (WCSB) blanket and a helium cooled solid breeder (HCSB) blanket, in the ITER Test Blanket Modules (TBM) programt.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::4a3cd41b6dc039088a0328288af56d05
http://www.scopus.com/inward/record.url?eid=2-s2.0-36248960578&partnerID=MN8TOARS
http://www.scopus.com/inward/record.url?eid=2-s2.0-36248960578&partnerID=MN8TOARS