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CNKI学位论文(1)
知网期刊论文(4)
在“
Elsevier电子期刊
”中,
命中:
17
条,耗时:小于0.01 秒
在所有数据库中总计命中:
5
条
1.
A study of plasma facing tungsten components with electrical discharge machined surface exposed to cyclic thermal loads
作者:
Yohji Seki
;
seki.yohji@jaea.go.jp" class="auth_mail" title="E-mail the corresponding author
;
Koichiro
Ezato
;
Satoshi Suzuki
;
Kenji Yokoyama
;
Hirokazu Yamada
;
Tomoyuki Hirayama
关键词:
Divertor
;
High heat flux
;
Plasma facing component
;
Tungsten
;
ITER
刊名:Fusion Engineering and Design
出版年:2016
2.
Development of high-grade VPS-tungsten coatings on F82H reduced activation steel
作者:
Tomonori Tokunaga
;
Hideo Watanabe
;
Naoaki Yoshida
;
Takuya Nagasaka
;
Ryuta Kasada
;
Young-Ju Lee
;
Akihiko Kimura
;
Masayuki Tokitani
;
Masatoshi Mitsuhara
;
Tatsuya Hinoki
;
Hideharu Nakashima
;
Suguru Masuzaki
;
Takeshi Takabatake
;
Nobuyoshi Kuroki
;
Koichiro
Ezato
;
Satoshi Suzuki
;
Masato Akiba
刊名:Journal of Nuclear Materials
出版年:2013
3.
Development of the plasma facing components in Japan for ITER
作者:
Satoshi Suzuki
;
Koichiro
Ezato
;
Yohji Seki
;
Kensuke Mohri
;
Kenji Yokoyama
;
Mikio Enoeda
关键词:
ITER
;
Divertor Outer Vertical Target
;
Full-scale prototype
;
Carbon fiber composite
;
Tungsten
刊名:Fusion Engineering and Design
出版年:2012
4.
Development of the Water Cooled Ceramic Breeder Test Blanket Module in Japan
作者:
Mikio Enoeda
;
Hisashi Tanigawa
;
Takanori Hirose
;
Satoshi Suzuki
;
Kentaro Ochiai
;
Chikara Konno
;
Yoshinori Kawamura
;
Toshihiko Yamanishi
;
Tsuyoshi Hoshino
;
Masaru Nakamichi
;
Hiroyasu Tanigawa
;
Koichiro
Ezato
;
Yohji Seki
;
Akira Yoshikawa
;
Daigo Tsuru
;
Masato Akiba
关键词:
Water Cooled Ceramic Breeder (WCCB) TBM
;
Fabrication technology
;
Prototypical size mockup
;
Advanced Li2TiO3
;
Fusion neutron tritium production experiments
刊名:Fusion Engineering and Design
出版年:2012
5.
R&D activities on manufacturing plasma-facing unit for prototype of ITER divertor outer target in JADA
作者:
Koichiro
Ezato
;
Satoshi Suzuki
;
Yohji Seki
;
Hiroshi Nishi
;
Kensuke Mohri
;
Mikio Enoeda
关键词:
ITER
;
Divertor
;
Plasma facing unit
;
Joint technology
;
Load carrying capability
刊名:Fusion Engineering and Design
出版年:2012
6.
Recent status of fabrication technology development of water cooled ceramic breeder test blanket module in Japan
作者:
Takanori Hirose
;
Hisashi Tanigawa
;
Akira Yoshikawa
;
Yohji Seki
;
Daigo Tsuru
;
Kenji Yokoyama
;
Koichiro
Ezato
;
Satoshi Suzuki
;
Mikio Enoeda
;
;
;
enoeda.mikio@jaea.go.jp
;
Masato Akiba
关键词:
ITER test blanket module
;
Water cooled ceramic breeder (WCCB) TBM
;
Fabrication technology
;
Prototypical size mockup
刊名:Fusion Engineering and Design
出版年:2011
7.
Non-destructive examination with infrared thermography system for ITER divertor components
作者:
Yohji Seki
;
Koichiro
Ezato
;
Satoshi Suzuki
;
Kenji Yokoyama
;
Mikio Enoeda
;
Seiji Mori
关键词:
ITER
;
Divertor
;
Thermography
;
Non-destructive examination
;
High heat flux
刊名:Fusion Engineering and Design
出版年:2010
8.
Heat transfer characteristics of the first wall with graphite sheet interlayer
作者:
Kei Masaki
;
Yasuhiko Miyo
;
Shinji Sakurai
;
Koichiro
Ezato
;
Satoshi Suzuki
;
Akira. Sakasai
关键词:
First wall
;
Carbon fiber composites
;
Graphite sheet
;
Contact heat transfer coefficient
刊名:Fusion Engineering and Design
出版年:2010
9.
Development of water-cooled solid breeder test blanket module in JAEA
作者:
Masato Akiba
;
Mikio Enoeda
;
Daigo Tsuru
;
Hisashi Tanigawa
;
Takanori Hirose
;
Kensuke Mohri
;
Yohji Seki
;
Koichiro
Ezato
;
Satoshi Suzuki
;
Hiroshi Nishi
;
Seiji Mori
关键词:
Blanket
;
Solid breeder
;
Water-cooled blanket
;
HIP
;
Test blanket module
;
Reduced activation ferritic steel
;
F82H
;
ITER
;
High-heat flux test
;
DATS
刊名:Fusion Engineering and Design
出版年:2009
10.
Experimental examination of heat removal limitation of screw cooling tube at high pressure and temperature conditions
作者:
Koichiro
Ezato
;
Satoshi Suzuki
;
Masayuki Dairaku and Masato Akiba
关键词:
High heat flux removal
;
Plasma-facing components
;
PFC
;
Fusion
;
Divertor
;
Screw tube
;
Heat transfer
;
Critical heat flux
刊名:Fusion Engineering and Design
出版年:2006
1
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