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SpringerLink电子期刊(41)
GSW全文库(3)
ACS电子期刊(3)
ProQuest学位论文(1)
Elsevier电子期刊(318)
在“
Elsevier电子期刊
”中,
命中:
318
条,耗时:0.0169845 秒
在所有数据库中总计命中:
366
条
1.
The use of representativity theory in the depletion calculations of SFR blankets
作者:
Jean-Franç
;
ois Lebrat
;
jean-francois.lebrat@cea.fr
;
Jean Tommasi
关键词:
Depletion calculation
;
SFR
;
Representativity factor
;
DARWIN
;
PHENIX
;
Sensitivities
;
Fuel
cycle
;
Uncertainty reduction
;
Transposition
刊名:Annals of Nuclear Energy
出版年:2017
2.
Hydrometallurgical Reprocessing of BREST-OD-300 Mixed Uranium-plutonium Nuclear
Fuel
作者:
A.Yu. Shadrin
a
;
shau@proryv2020.ru
;
K.N. Dvoeglazov
a
;
V.A. Kascheyev
a
;
V.L. Vidanov
a
;
V.I. Volk
b
;
S.N. Veselov
b
;
B.Ya. Zilberman
c
;
D.V. Ryabkov
c
关键词:
uranium plutonium mixed
fuel
;
nitride
fuel
;
SNF reprocessing
;
hydrometallurgy
刊名:Procedia Chemistry
出版年:2016
3.
The effect of a changing
fuel
solution composition on a transient in a
fissile
solution
作者:
M. Major
a
;
C.M. Cooling
b
;
c.cooling10@imperial.ac.uk" class="auth_mail" title="E-mail the corresponding author
;
M.D. Eaton
b
关键词:
Fissile
solutions
;
Criticality
;
Transients
刊名:Progress in Nuclear Energy
出版年:2016
4.
A simulation study of the spent nuclear
fuel
cask condition evaluation using high energy X-ray computed tomography
作者:
Xin Liu
;
Hyoung Koo Lee
关键词:
Spent nuclear
fuel
;
Cask
;
High-energy X-ray
;
Computed tomography
;
Iterative reconstruction
刊名:NDT and E International
出版年:2016
5.
Power transient analysis of
fuel
-loaded reflector experimental devices in Jules Horowitz Material Testing Reactor
作者:
P. Console Camprini
a
;
patrizio.consolecamprini@enea.it" class="auth_mail" title="E-mail the corresponding author
;
M. Sumini
b
;
C. Artioli
a
;
1
;
C. Gonnier
c
;
B. Pouchin
c
;
P. Sireta
c
;
S. Bourdon
c
关键词:
MTR
;
Jules Horowitz Reactor
;
JHR
;
Research reactor
;
Power transient
;
Fuel
sample
;
Point kinetics
;
Core-reflector coupling
刊名:Annals of Nuclear Energy
出版年:2016
6.
Thorium utilization in existing and advanced reactor types
作者:
V. Jagannathan
a
;
v_jagan1952@rediffmail.com" class="auth_mail" title="E-mail the corresponding author
;
Arvind Mathur
b
;
Suhail Ahmad Khan
c
关键词:
Fissile
breeding
;
Thorium breeders
;
Advanced reactor design
刊名:International Journal of Hydrogen Energy
出版年:2016
7.
Studies of MYRRHA using thorium
fuel
作者:
Roger Barlow
a
;
Roger.Barlow@hud.ac.uk" class="auth_mail" title="E-mail the corresponding author
;
James Burlison
a
;
Tristan Edwards
a
;
Alisa Healy
a
;
Alex Masterson
a
;
Hamid Aï
;
t Abderrahim
b
;
Edouard Malambu
b
;
Gert van den Eynde
b
关键词:
ADSR
;
MA waste
;
Thorium
;
Transmutation
刊名:International Journal of Hydrogen Energy
出版年:2016
8.
Thermal cycling effect in U-10Mo/Zry-4 monolithic nuclear
fuel
作者:
Denise A. Lopes
a
;
deniseadorno@hotmail.com" class="auth_mail" title="E-mail the corresponding author
;
Angelo J.O. Zimmermann
b
;
Selma L. Silva
b
;
J.R.C. Piqueira
a
刊名:Journal of Nuclear Materials
出版年:2016
9.
Monte Carlo calculations of the nuclear effects of certain fluids in a hybrid reactor
作者:
Mehtap Gü
;
nay
;
mehtap.gunay@inonu.edu.tr" class="auth_mail" title="E-mail the corresponding author
关键词:
TBR
;
M
;
Heat deposition rate
;
Fissile
fuel
breeding
;
Radiation damage
;
MCNPX-2.7.0
刊名:Progress in Nuclear Energy
出版年:2016
10.
Core design optimization and analysis of the Purdue Novel Modular Reactor (NMR-50)
作者:
Faisal Y. Odeh
;
Won Sik Yang
;
yang494@purdue.edu" class="auth_mail" title="E-mail the corresponding author
关键词:
SMR
;
small modular reactor
;
NMR
;
Novel Modular Reactor
;
BOC
;
beginning of cycle
;
EOC
;
end of cycle
;
VC
;
void coefficient
;
MCPR
;
minimum critical power ratio
;
MFLPD
;
maximum
fuel
linear power density
;
SDM
;
shutdown margin
;
PMAXS
;
Purdue Macroscopic Cross-Section
;
S3C
;
SIMULATE-3 case matrix
;
CHF
;
critical heat flux
;
BP
;
burnable poison
;
Gd
;
gadolinium
;
SA
;
simulated annealing
;
FA
;
fuel
assembly
;
AO
;
axial offset
;
O-2
;
Oskarshamn-2
刊名:Annals of Nuclear Energy
出版年:2016
1
2
3
4
5
6
7
8
9
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