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SpringerLink电子期刊(3)
Elsevier电子期刊(53)
在“
Elsevier电子期刊
”中,
命中:
53
条,耗时:0.0109674 秒
在所有数据库中总计命中:
56
条
1.
TPE upgrade for enhancing operational safety and improving in-
vessel
tritium
inventory
assessment in fusion nuclear environment
作者:
M. Shimada
a
;
Masashi.Shimada@inl.gov" class="auth_mail" title="E-mail the corresponding author
;
C.N. Taylor
a
;
L. Moore-McAteer
a
;
R.J. Pawelko
a
;
R.D. Kolasinski
b
;
D.A. Buchenauer
b
;
L.C. Cadwallader
a
;
B.J. Merrill
a
关键词:
Tritium
plasma experiment
;
Tritium
in-
vessel
inventory
;
Neutron-irradiated materials
刊名:Fusion Engineering and Design
出版年:2016
2.
In-
vessel
dust and
tritium
control strategy in ITER
作者:
M. Shimada
;
michiya.shimada@iter.org
;
R.A. Pitts
;
S. Ciattaglia
;
S. Carpentier
;
C.H. Choi
;
G. Dell Orco
;
T. Hirai
;
A. Kukushkin
;
S. Lisgo
;
J. Palmer
;
W. Shu
;
E. Veshchev
刊名:Journal of Nuclear Materials
出版年:2013
3.
F4E R&D programme and results on in-
vessel
dust and
tritium
作者:
F. Le Guern
a
;
;
frederic.leguern@f4e.europa.eu
;
W. Gulden
a
;
S. Ciattaglia
b
;
G. Counsell
a
;
A. Bengaouer
c
;
J. Brinster
c
;
F. Dabbene
c
;
A. Denkevitz
d
;
T. Jordan
d
;
M. Kuznetsov
d
;
M.T. Porfiri
e
;
R. Redlinger
d
;
Ph. Roblin
c
;
J. Roth
f
;
J. Segré
;
c
;
K. Sugiyama
f
;
I. Tkatschenko
c
;
Z. Xu
d
关键词:
Fusion
;
Tokamak
;
ITER
;
Safety
;
Diagnostics
;
Dust
;
Tritium
刊名:Fusion Engineering and Design
出版年:2011
4.
Tritium
fuel cycle in ITER and DEMO: Issues in handling large amount of fuel
作者:
T. Tanabe
tanabe@nucl.kyushu-u.ac.jp
刊名:Journal of Nuclear Materials
出版年:2013
5.
Desorption of deuterium from beryllium codeposits using flash heating
作者:
J.H. Yu
a
;
jyu@ferp.ucsd.edu
;
M.J. Baldwin
a
;
R.P. Doerner
a
;
R.A. Pitts
b
;
R.D. Smirnov
a
;
H.W. Xu
c
刊名:Journal of Nuclear Materials
出版年:2013
6.
Fuel hydrogen retention of tungsten and the reduction by inert gas glow discharges
作者:
T. Hino
;
Y. Yamauchi
;
Y. Kimura
;
K. Nishimura
;
Y. Ueda
关键词:
Tungsten
;
Deuterium retention
;
Tritium
retention
;
Glow discharge
;
Helium
;
Neon
;
Argon
;
Hydrogen isotope exchange
;
Wall baking
刊名:Fusion Engineering and Design
出版年:2012
7.
Development of a Laser Ablation System Kit (LASK) for Tokamak in
vessel
tritium
and dust
inventory
control
作者:
C. Hern
;
ez
;
H. Roche
;
C. Pocheau
;
C. Grisolia
;
L. Gargiulo
;
A. Semerok
;
A. Vatry
;
P. Delaporte
;
L. Mercadier
关键词:
Laser ablation
;
LIBS
;
Dust recovery
;
Integration
刊名:Fusion Engineering and Design
出版年:2009
8.
Process simulation for fuel delivery from storage and delivery system in fusion power plant
作者:
Min Ho Chang
a
;
;
mhchang@nfri.re.kr
;
Seungyon Cho
a
;
Hyun-Goo Kang
a
;
Sei-Hun Yun
a
;
Kyu-Min Song
b
;
Dukjin Kim
c
;
Hongsuk Chung
d
关键词:
Storage and delivery system
;
Fuel delivery
;
Parameter analysis
;
Numerical process simulation
刊名:Fusion Engineering and Design
出版年:2011
9.
Study on the fuel balance of a DT reactor
作者:
Masabumi Nishikawa
;
Tetsuo Tanabe
关键词:
Tritium
balance
;
Recovery efficiency
;
Burning efficiency
;
Trapping efficiency
刊名:Fusion Engineering and Design
出版年:2010
10.
Preliminary
tritium
safety analysis on China DFLL-TBM for ITER
作者:
Yong Song
;
Qunying Huang
;
Muyi Ni
;
Yongliang Wang
关键词:
Tritium
;
Safety analysis
;
Test blanket module
;
Liquid LiPb
刊名:Fusion Engineering and Design
出版年:2009
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