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内部出版物
SpringerLink电子期刊(6)
ProQuest学位论文(2)
Elsevier电子期刊(199)
在“
Elsevier电子期刊
”中,
命中:
199
条,耗时:0.1159446 秒
在所有数据库中总计命中:
207
条
1.
SFR mechanical scenarios and neutron transport transients with CAST3M code
作者:
Grzegorz Kępisty
a
;
gkepisty@agh.edu.pl
;
Cyril Patricot
b
;
cyril.patricot@cea.fr
;
Daniel Broc
c
;
daniel.broc@cea.fr
;
Guillaume Campioni
b
;
guillaume.campioni@cea.fr
关键词:
SFR
;
Sodium Fast
Reactor
;
CFSI
;
Cast3M Fluid-Structure Interaction (tool)
;
CNTT
;
Cast3M Neutron Transport Tool
;
CEA
;
Atomic Energy and Alternative Energies Commission
;
FSI
;
Fluid-Structure Interaction
;
FEM
;
Finite Element Method
;
LNP
;
Lateral Neutron Protection
;
FA
;
Fuel Assembly
;
CR
;
Control Rod
;
EOL
;
End
-
of
-Life
刊名:Annals
of
Nuclear
Energy
出版年:2017
2.
A Criticality Analysis
of
the GBC-32 Dry Storage Cask with Hanbit
Nuclear
Power Plant Unit 3 Fuel Assemblies from the Viewpoint
of
Burnup Credit
作者:
Hyungju Yun
;
Do-Yeon Kim
;
Kwangheon Park
;
Ser Gi Hong
;
sergihong@khu.ac.kr" class="auth_mail" title="E-mail the corresponding author
关键词:
Axial Burnup Distribution
;
Burnup Credit
;
Dry Storage Cask
;
Monte Carlo N-Particle Transport Code
;
Version 6
;
Nuclear
Criticality
Safe
ty Analysis
;
SCALE 6.1/STandardized Analysis
of
Reactivity for Burnup Credit using SCALE
刊名:
Nuclear
Engineering and Technology
出版年:2016
3.
Overall System Description and
Safe
ty Characteristics
of
Prototype Gen IV Sodium Cooled Fast
Reactor
in Korea
作者:
Jaewoon Yoo
;
jwyoo@kaeri.re.kr" class="auth_mail" title="E-mail the corresponding author
;
Jinwook Chang
;
Jae-Yong Lim
;
Jin-Sik Cheon
;
Tae-Ho Lee
;
Sung Kyun Kim
;
Kwi Lim Lee
;
Hyung-Kook Joo
关键词:
Inherent
Safe
ty
;
Metal Fuel
;
Passive
Safe
ty
;
Pool Type
;
Sodium Cooled Fast
Reactor
刊名:
Nuclear
Engineering and Technology
出版年:2016
4.
Study on Limit Loads for
Safe
End
of
Nuclear
Pressure Vessel with Local Wall Thinning
作者:
J. Li
a
;
P. Cui
a
;
G.D. Zhang
b
;
F. Xue
b
;
C.Y. Zhou
a
;
changyu_zhou@163.com" class="auth_mail" title="E-mail the corresponding author
关键词:
local wall thinning
;
safe
end
of
nuclear
reactor
;
limit load
;
finite element
刊名:Procedia Engineering
出版年:2015
5.
Optimising differential data formats for Monte-Carlo radiation transport in the fusion regime
作者:
T. Hutton
a
;
b
;
dr.t.hutton@gmail.com" class="auth_mail" title="E-mail the corresponding author
;
J-Ch. Sublet
b
;
L. Morgan
b
;
T.W. Leadbeater
a
关键词:
Nuclear
data pre-processing
;
MCNP
;
Nuclear
fusion
刊名:Annals
of
Nuclear
Energy
出版年:2016
6.
Technical reliability
of
active fire protection features - generic database derived from German
nuclear
power plants
作者:
Burkhard Forell
a
;
burkhard.forell@grs.de" class="auth_mail" title="E-mail the corresponding author
;
Jö
;
rg Peschke
a
;
Svante Einarsson
b
;
Marina Rö
;
wekamp
a
关键词:
Fire PSA
;
Reliability data
;
Failure rate per hours
of
plant operation
;
Fault trees for technical component failures
刊名:Reliability Engineering & System
Safe
ty
出版年:2016
7.
Improving collaborative work and project management in a
nuclear
power plant design team: A human-centered design approach
作者:
Guy André
;
Boy
a
;
gboy@fit.edu" class="auth_mail" title="E-mail the corresponding author
;
guy.andre.boy@gmail.com" class="auth_mail" title="E-mail the corresponding author
Author Vitae
;
Gopal Jani
a
;
Annalisa Manera
b
;
Matthew Memmott
c
;
Bojan Petrovic
d
;
Yassine Rayad
a
;
Lucas Stephane
a
;
Neha Suri
a
关键词:
Human-centered design
;
Computer-supported cooperative work
;
Modeling and simulation
;
Knowledge management
;
Project management
刊名:Annals
of
Nuclear
Energy
出版年:2016
8.
Irradiation performance
of
(Th,Pu)O
2
fuel under Pressurized Water
Reactor
conditions
作者:
B. Boer
a
;
brian.boer@sckcen.be" class="auth_mail" title="E-mail the corresponding author
;
S. Lemehov
a
;
M. Wé
;
ber
a
;
Y. Parthoens
a
;
M. Gysemans
a
;
J. McGinley
b
;
J. Somers
b
;
M. Verwerft
a
关键词:
Thorium fuel
;
Irradiation performance
;
Fission gas release
刊名:Journal
of
Nuclear
Materials
出版年:2016
9.
Probabilistic Fracture Mechanics Analysis
of
Boling Water
Reactor
Vessel for Cool-Down and Low Temperature Over-Pressurization Transients
作者:
Jeong Soon Park
;
Young Hwan Choi
;
Myung Jo Jhung
;
mjj@kins.re.kr" class="auth_mail" title="E-mail the corresponding author
关键词:
Cool-Down
;
Low Temperature Over-Pressurization
;
Probabilistic Fracture Mechanics
;
Reactor
Pressure Vessel
刊名:
Nuclear
Engineering and Technology
出版年:2016
10.
A Lattice-Based Monte Carlo Evaluation
of
Canada Deuterium Uranium-6
Safe
ty Parameters
作者:
Yonghee Kim
;
yongheekim@kaist.ac.kr" class="auth_mail" title="E-mail the corresponding author
;
Donny Hartanto
1
;
Woosong Kim
关键词:
CANada Deuterium Uranium
;
Doppler Broadening Rejection Correction
;
Fuel Temperature Coefficient
;
Monte Carlo
;
Power Coefficient
of
Reactivity
刊名:
Nuclear
Engineering and Technology
出版年:2016
1
2
3
4
5
6
7
8
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