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内部出版物
CNKI学位论文(11)
知网期刊论文(15)
在“
Elsevier电子期刊
”中,
命中:
69
条,耗时:小于0.01 秒
在所有数据库中总计命中:
26
条
1.
Impact analysis of the time trend of TBR and irradiation damage assessment of HCSB
blanket
for CFETR
作者:
Qin Zeng
;
zengqin@ustc.edu.cn
;
Hongli Chen
;
Zhongliang Lv
;
Lei Pan
;
Haoran Zhang
;
Wei Shi
关键词:
Helium cooled solid
breeder
blanket
;
the time trend of TBR
;
Irradiation damage
;
3D neutronics model
刊名:Fusion Engineering and Design
出版年:2017
2.
Material analyses of foam-based SiC FCI after dynamic testing in PbLi in MaPLE loop at UCLA
作者:
Maria Gonzalez
a
;
maria.gonzalez@ciemat.es" class="auth_mail" title="E-mail the corresponding author
;
David Rapisarda
a
;
Angel Ibarra
a
;
Cyril Courtessole
b
;
Sergey Smolentsev
b
;
Mohamed Abdou
b
关键词:
FCI development
;
Dual
coolant
lead
lithium
breeder
blanket
concept
;
DCLL
;
Silicon carbide
;
SiC
;
Material characterization
刊名:Fusion Engineering and Design
出版年:2016
3.
Design activities toward the achievement of the
concept
ual phase of the EU-TBM sets
作者:
J. Vallory
a
;
Joelle.vallory@f4e.europa.eu" class="auth_mail" title="E-mail the corresponding author
;
D. Panayotov
a
;
M. Zmitko
a
;
Y. Poitevin
a
;
F.J. Calvo Plaza
b
;
S. Sadaba
b
;
A. Gil
b
关键词:
Design
;
Structural analysis
;
Thermo mechanical analysis
;
TBM
;
ITER
刊名:Fusion Engineering and Design
出版年:2016
4.
Engineering design and analysis of Indian LLCB TBM set
作者:
S. Ranjithkumar
a
;
ranjith@ipr.res.in" class="auth_mail" title="E-mail the corresponding author
;
Deepak Sharma
a
;
Paritosh Chaudhuri
a
;
Chandan Danani
a
;
E. Rajendra Kumar
a
;
Istiyak Khan
b
;
Sujay Bhattacharya
b
;
K.N. Vyas
b
关键词:
ITER
;
LLCB TBM
;
Shield block
;
Structural analysis
;
ANSYS
刊名:Fusion Engineering and Design
出版年:2016
5.
Neutronic investigations of a laser fusion driven
lithium
cooled thorium
breeder
作者:
Sü
;
mer 艦ahin
a
;
ssahin@atilim.edu.tr" class="auth_mail
;
sumersahin@yahoo.com" class="auth_mail
;
;
Ba艧ar 艦arer
b
;
Yurdunaz Ç
;
elik
c
关键词:
Inertial confinement fusion
;
Thorium
;
TRISO particles
;
Natural
lithium
coolant
;
Tritium breeding
刊名:Progress in Nuclear Energy
出版年:May, 2014
6.
Finalization of the
concept
ual design of the auxiliary circuits for the European test
blanket
systems
作者:
A. Aiello
a
;
antonio.aiello@enea.it" class="auth_mail" title="E-mail the corresponding author
;
B.E. Ghidersa
b
;
M. Utili
a
;
L. Vala
c
;
T. Ilkei
d
;
G. Di Gironimo
e
;
R. Mozzillo
e
;
A. Tarallo
e
;
I. Ricapito
f
;
P. Calderoni
f
关键词:
Breeding
blanket
;
Integration in ITER
;
Tritium extraction and management
刊名:Fusion Engineering and Design
出版年:2015
7.
Metallurgical analysis of corroded bellows of bellow-sealed valve in
lithium
flow system
作者:
Asril Pramutadi Andi Mustari
a
;
Minoru Takahashi
b
;
mtakahas@nr.titech.ac.jp
关键词:
Lithium
;
Bellows
;
Bellow-sealed valve
;
Cold work
;
Corrosion
;
Fatigue
刊名:Fusion Engineering and Design
出版年:2013
8.
Tritium transport analysis in HCPB DEMO
blanket
with the FUS-TPC code
作者:
F. Franza
;
L.V. Boccaccini
;
A. Ciampichetti
;
M. Zucchetti
关键词:
Tritium
;
Permeation
;
DEMO
;
HCPB
;
Blanket
;
Lithium
&ndash
;
orthosilicate
刊名:Fusion Engineering and Design
出版年:2013
9.
An example pathway to a fusion power plant system based on
lead
–
lithium
breeder
: Comparison of the
dual
-
coolant
lead
–
lithium
(DCLL)
blanket
with the helium-cooled
lead
–
lithium
(HCLL)
concept
as initial step
作者:
S. Malang
;
A.R. Raffray
;
N.B. Morley
关键词:
Dual
-
coolant
lead
–
;
lithium
blanket
;
He-cooled
lead
–
;
lithium
blanket
;
Pathway to power plant
concept
刊名:Fusion Engineering and Design
出版年:2009
10.
An effect of heavy water in a Korean DEMO water cooled ceramic
blanket
(WCCB)
作者:
Young Seok Lee
;
Keeman Kim
;
Jun Ho Yeom
;
Hyoung Chan Kim
;
Kihak Im
关键词:
Korean DEMO Reactor (K-DEMO)
;
Water-cooled ceramic
blanket
(WCCB)
;
Heavy water (D2O)
;
Light water (H2O)
;
TBR
刊名:Fusion Engineering and Design
出版年:2013
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