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Elsevier电子期刊(12)
在“
Elsevier电子期刊
”中,
命中:
12
条,耗时:小于0.01 秒
在所有数据库中总计命中:
12
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 residual thermal stress-relieving structure of CFC monoblock target for JT-60SA divertor
作者:
Daigo Tsuru
;
tsuru.daigo@jaea.go.jp" class="auth_mail" title="E-mail the corresponding author
;
Shinji Sakurai
;
Shigetoshi Nakamura
;
Hidetsugu Ozaki
;
Yohji
Seki
;
Kenji Yokoyama
;
Satoshi Suzuki
关键词:
CFC monoblock target
;
Vacuum brazing
;
Residual thermal stress
;
Numerical simulation
;
Infrared thermography inspection
;
High heat flux test
刊名:Fusion Engineering and Design
出版年:2015
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.
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
5.
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
6.
Development of a two-dimensional nuclear-thermal-coupled analysis code for conceptual blanket design of fusion reactors
作者:
Hiroyasu Utoh
;
;
;
uto.hiroyasu@jaea.go.jp
;
Kenji Tobita
;
Youji Someya
;
Satoshi Sato
;
Yohji
Seki
;
Haruhiko Takase
关键词:
Blanket
;
Design
;
Fusion reactor
;
Nuclear analysis
;
Thermal analysis
;
DOT3.5
刊名:Fusion Engineering and Design
出版年:2011
7.
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
8.
Packing experiment of breeder pebbles into water cooled solid breeder test blanket module for ITER
作者:
Takanori Hirose
;
Yohji
Seki
;
Hisashi Tanigawa
;
Hiroyasu Tanigawa
;
Daigo Tsuru
;
Mikio Enoeda
;
Hisashi Serizawa
;
Hiroto Yamaoka
关键词:
Reduced activation ferritic/martensitic steel
;
Blanket
;
Ceramic breeder
;
Pebble bed
刊名:Fusion Engineering and Design
出版年:2010
9.
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
10.
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
1
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