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SpringerLink电子期刊(45)
NATURE电子期刊(1)
Elsevier电子期刊(612)
在“
Elsevier电子期刊
”中,
命中:
612
条,耗时:小于0.01 秒
在所有数据库中总计命中:
658
条
1.
Numerical research on the neutronic/thermal-hydraulic/mechanical coupling characteristics of the optimized helium cooled solid breeder
blanket
for CFETR
作者:
Shijie Cui
;
Dalin Zhang
;
dlzhang@mail.xjtu.edu.cn
;
Jie Cheng
;
Wenxi Tian
;
G.H. Su
关键词:
CFETR
;
Blanket
;
Coupling analysis
;
Neutronics
;
Thermal-hydraulics
;
Thermo-mechanics
刊名:Fusion Engineering and Design
出版年:2017
2.
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
3.
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
4.
Model and simulation of a vacuum sieve tray for T extraction from liquid PbLi
breeding
blanket
s
作者:
M.A.J. Mertens
a
;
1
;
merlijn.mertens@ugent.be" class="auth_mail" title="E-mail the corresponding author
;
D. Demange
b
;
david.demange@kit.edu" class="auth_mail" title="E-mail the corresponding author
;
L. Frances
b
;
laetitia.frances@kit.edu" class="auth_mail" title="E-mail the corresponding author
关键词:
Fusion
;
Breeding
blanket
;
Liquid PbLi
;
Tritium extraction system
;
Vacuum sieve tray
;
Size estimation
刊名:Fusion Engineering and Design
出版年:2016
5.
Dynamic thermal-hydraulic modelling of the EU DEMO HCPB
breeding
blanket
cooling loops
作者:
A. Froio
a
;
C. Bachmann
b
;
F. Cismondi
b
;
L. Savoldi
a
;
R. Zanino
a
;
roberto.zanino@polito.it" class="auth_mail" title="E-mail the corresponding author
关键词:
Nuclear fusion
;
DEMO
;
Breeding
blanket
;
HCPB
;
Cooling circuit
;
Thermal-hydraulics
;
Modelling
刊名:Progress in Nuclear Energy
出版年:2016
6.
Conceptual design of a First Wall mock-up experiment in preparation for the qualification of
breeding
blanket
technologies in the Helium Loop Karlsruhe (HELOKA) facility
作者:
C. Zeile
a
;
christian.zeile@kit.edu" class="auth_mail" title="E-mail the corresponding author
;
A. Abou-Sena
a
;
L.V. Boccaccini
a
;
B.E. Ghidersa
a
;
Q. Kang
a
;
A. Kunze
a
;
L. Lamberti
a
;
b
;
I.A. Maione
a
;
J. Rey
a
;
A. von der Weth
a
关键词:
Breeding
blanket
;
High heat flux
;
Qualification
;
HELOKA
刊名:Fusion Engineering and Design
出版年:2016
7.
Current design of the European TBM systems and implications on DEMO
breeding
blanket
作者:
Ricapito
a
;
;
P. Calderoni
a
;
A. Aiello
b
;
B. Ghidersa
c
;
Y. Poitevin
a
;
J. Pacheco
a
关键词:
Breeding
blanket
;
Test
Blanket
System
;
Tritium extraction
刊名:Fusion Engineering and Design
出版年:2016
8.
Nuclear-thermal-coupled optimization code for the fusion
breeding
blanket
conceptual design
作者:
Jia Li
a
;
lijia@ustc.edu.cn
;
Kecheng Jiang
b
;
Xiaokang Zhang
b
;
Xingchen Nie
a
;
Qinjun Zhu
b
;
Songlin Liu
b
关键词:
Blanket
;
Nuclear-thermal coupling
;
Radial build optimization
刊名:Fusion Engineering and Design
出版年:2016
9.
Methodology for accident analyses of fusion breeder
blanket
s and its application to helium-cooled pebble bed
blanket
作者:
Dobromir Panayotov
a
;
dobromir.panayotov@f4e.europa.eu" class="auth_mail" title="E-mail the corresponding author
;
Andrew Grief
b
;
Brad J. Merrill
c
;
Paul Humrickhouse
c
;
Martin Trow
b
;
Michael Dillistone
b
;
Julian T. Murgatroyd
b
;
Simon Owen
b
;
Yves Poitevin
a
;
Karen Peers
b
;
Alex Lyons
b
;
Adam Heaton
b
;
Richard Scott
b
关键词:
Fusion safety
;
Fusion breeder
blanket
s
;
Accident analyses
;
ITER
;
DEMO
;
Test
blanket
system
刊名:Fusion Engineering and Design
出版年:2016
10.
Objectives and status of EUROfusion DEMO
blanket
studies
作者:
L.V. Boccaccini
a
;
lorenzo.boccaccini@kit.edu" class="auth_mail" title="E-mail the corresponding author
;
G. Aiello
b
;
J. Aubert
b
;
C. Bachmann
c
;
T. Barrett
d
;
A. Del Nevo
e
;
D. Demange
a
;
L. Forest
b
;
F. Hernandez
a
;
P. Norajitra
a
;
G. Porempovic
f
;
D. Rapisarda
g
;
P. Sardain
h
;
M. Utili
e
;
L. Vala
i
关键词:
Breeding
blanket
;
DEMO
;
Tokamak
;
In-vessel components
;
PbLi loops
;
Tritium extraction
刊名:Fusion Engineering and Design
出版年:2016
1
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