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CNKI学位论文(3)
知网期刊论文(2)
在“
Elsevier电子期刊
”中,
命中:
16
条,耗时:小于0.01 秒
在所有数据库中总计命中:
5
条
1.
Status on DEMO Helium Cooled Lithium Lead breeding
blanket
thermo-mechanical analyses
作者:
J. Aubert
a
;
julien.aubert@cea.fr" class="auth_mail" title="E-mail the corresponding author
;
G. Aiello
a
;
J.-C. Jaboulay
a
;
B. Kiss
b
;
A. Morin
a
关键词:
DEMO
;
Breeding
Blanket
;
HCLL
;
Design
;
Cast3M
;
RCC-MRx
刊名:Fusion Engineering and Design
出版年:2016
2.
Status of ITER
blanket
attachment design and related R&D
作者:
S. Sadakov
;
S. Khomiakov
;
B. Calcagno
;
Ph. Chappuis
;
G. Dellopoulos
;
V. Kolganov
;
M. Merola
;
I. Poddubnyi
;
R. Raffray
;
J.J. Raharijaona
;
M. Ulrickson
;
A. Zhmakin
;
All contributors to the BIPT effort
关键词:
ITER
;
Blanket
attachments
;
Flexible supports
;
Key pads
;
Ceramic coating
;
Electrical straps
刊名:Fusion Engineering and Design
出版年:2013
3.
Attachment systems for demo in-vessel components:
Blanket
, manifold and hot ring shield
作者:
C. Koehly
;
D. Filsinger
;
D. Nagy
;
C. Polixa
;
J. Rey
关键词:
Fusion
;
Demo
;
HCPB
;
Blanket
;
Attachment
;
Integration
刊名:Fusion Engineering and Design
出版年:2008
4.
Properties of unirradiated and irradiated Ti-6Al-4V alloy for ITER flexible connectors
作者:
B.S. Rodchenkov
a
;
rodchen@nikiet.ru
;
M.V. Evseev
b
;
Yu.S. Strebkov
a
;
L.P. Sinelnikov
b
;
V.V. Shushlebin
b
刊名:Journal of Nuclear Materials
出版年:2011
5.
Design approach for the main ITER test
blanket
modules for the EU helium cooled lithium–lead
blanket
s
作者:
G. Rampal
;
D. Gatelet
;
L. Giancarli
;
G. Laffont
;
A. Li-Puma
;
J.F. Salavy and E. Rigal
关键词:
HCLL
;
Test
blanket
module design
刊名:Fusion Engineering and Design
出版年:2006
6.
Conceptual design of the ITER upper port plug for charge exchange diagnostic
作者:
S. Sadakov
;
T. Baross
;
W. Biel
;
V. Borsuk
;
N. Hawkes
;
M. von Hellermann
;
P. Gille
;
G. Kiss
;
J. Koning
;
M. Knaup
;
F. Klinkhamer
;
Yu. Krasikov
;
A. Litnovsky
;
O. Neubauer
;
A. Panin
关键词:
ITER core charge exchange diagnostic
;
Upper port plug
;
First mirror
;
Shutter
;
Attachments
;
Electromagnetic loads
刊名:Fusion Engineering and Design
出版年:2009
7.
Attachment concept for the “multi module segments” in a pulsed DEMO reactor
作者:
Enrico Magnani
;
Ali Abou-Sena
;
Fabio Cismondi
;
Nicola Scheel
;
Daniel Nagy
;
Pavel Pereslavtsev
;
Riccardo Roccella
;
Thomas Ihli
关键词:
Fusion
;
Design
;
Integration
;
Attachment
;
DEMO
;
FEM
刊名:Fusion Engineering and Design
出版年:2009
8.
Irradiation behavior of Ti–4Al–2V (ΠT-3B) alloy for ITER
blanket
modules flexible attachment
作者:
B.S. Rodchenkov
;
A.V. Kozlov
;
Yu.G. Kuznetsov
;
G.M. Kalinin
;
Yu.S. Strebkov
关键词:
Glasses
;
Mechanical properties
;
Crack growth
刊名:Journal of Nuclear Materials
出版年:2007
9.
Recent progress of ITER FW/
blanket
design and preparations for fabrication
作者:
K. Ioki
;
F. Elio
;
M. Nakahira
;
J. Ohmori
;
M. Shimada
;
M. Sugihara
;
X. Wang and for ITER International Team and Participant Teams
关键词:
ITER
;
Blanket
;
First wall
;
Attachments
;
Supports
;
Dynamic effect
刊名:Fusion Engineering and Design
出版年:2006
10.
Design and R&D progress of
blanket
attachments
作者:
Elio
;
F.
;
Ioki
;
K.
;
Yamada
;
M.
;
Strebkov
;
Y.
;
Daenner
;
W.
;
Akiba
;
M.
关键词:
ITER
;
Vessel
;
Coolant
;
Blanket
;
Supports
;
Connector
;
Strap
;
Bolt weld
刊名:Fusion Engineering and Design
出版年:2003
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