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Elsevier电子期刊(8)
在“
Elsevier电子期刊
”中,
命中:
8
条,耗时:小于0.01 秒
在所有数据库中总计命中:
8
条
1.
Design study of blanket structure based on a water-cooled solid breeder for DEMO
作者:
Youji Someya
;
Kenji Tobita
;
Hiroyasu
Utoh
;
Shinji Tokunaga
;
Kazuo Hoshino
;
Nobuyuki Asakura
;
Makoto Nakamura
;
Yoshiteru Sakamoto
关键词:
Breeding blanket
;
Water-cooled solid breeder
;
DEMO
刊名:Fusion Engineering and Design
出版年:2015
2.
Comparative evaluation of remote maintenance schemes for fusion DEMO reactor
作者:
Hiroyasu
Utoh
;
uto.
hiroyasu
@jaea.go.jp" class="auth_mail" title="E-mail the corresponding author
;
Kenji Tobita
;
Youji Someya
;
Nobuyuki Asakura
;
Yoshiteru Sakamoto
;
Kazuo Hoshino
;
Makoto Nakamura
关键词:
Remote maintenance
;
DEMO
;
Segment
;
Sector transport
;
Fusion reactor
刊名:Fusion Engineering and Design
出版年:2015
3.
Impact of an ¡®inter linked¡¯ central solenoid configuration on the size of tokamak DEMO
作者:
Makoto Nakamura
;
Kenji Tobita
;
Hiroyasu
Utoh
;
Yoshiteru Sakamoto
关键词:
Inter-linked central solenoid
;
Magnetic flux swing
;
Plasma current ramp-up
;
Systems analysis
;
Fusion reactor design
刊名:Fusion Engineering and Design
出版年:2013
4.
Waste management strategy focused on maintenance, storage and recycling
作者:
Youji Someya
;
Kenji Tobita
;
Hiroyasu
Utoh
;
Nobuyuki Asakura
关键词:
Waste management
;
Maintenance
;
Decay heat
;
Sector transport
;
SlimCS
刊名:Fusion Engineering and Design
出版年:2012
5.
Efforts towards improvement of systems codes for the Broader Approach DEMO design
作者:
Makoto Nakamura
;
Richard Kemp
;
Hiroyasu
Utoh
;
David J. Ward
;
Kenji Tobita
;
Ryoji Hiwatari
;
Gianfranco Federici
关键词:
Systems codes
;
Benchmarking
;
DEMO
;
Reactor design
;
The Broader Approach
;
Zero-dimensional model
刊名:Fusion Engineering and Design
出版年:2012
6.
Conceptual study of vertical sector transport maintenance for DEMO fusion reactor
作者:
Hiroyasu
Utoh
;
Kenji Tobita
;
Youji Someya
;
Haruhiko Takase
关键词:
Maintenance
;
Vertical sector transport
;
DEMO
;
Design
;
Fusion reactor
刊名:Fusion Engineering and Design
出版年:2012
7.
Development of a two-dimensional nuclear-thermal-coupled analysis code for conceptual blanket design of fusion reactors
作者:
Hiroyasu
Utoh
xA0
;
;
xA0
;
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
8.
Simplification of blanket system for SlimCS fusion DEMO reactor
作者:
Youji Someya
xA0
;
;
xA0
;
someya.yoji@jaea.go.jp
;
Haruhiko Takase
;
Hiroyasu
Utoh
;
Kenji Tobita
;
Changle Liu
;
Nobuyuki Asakura
关键词:
Mixed breeder blanket
;
Demo
;
SlimCS
;
Neutronics
;
Thermal analysis
刊名:Fusion Engineering and Design
出版年:2011
1
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作者(8)
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2015年(2)
2013年(1)
2012年(3)
2011年(2)
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