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内部出版物
Wiley电子期刊(3)
NATURE电子期刊(1)
Elsevier电子期刊(351)
SpringerLink电子期刊(92)
GSW全文库(1)
ACS电子期刊(15)
在“
Elsevier电子期刊
”中,
命中:
351
条,耗时:0.0749635 秒
在所有数据库中总计命中:
463
条
1.
Dominance ratio evolution in large thermal reactors
作者:
G. Kępisty
;
gkepisty@agh.edu.pl
;
J. Cetnar
关键词:
BOC
;
beginning of cycle
;
DR
;
Dominance Ratio
;
EFPD
;
Equivalent Full Power Day
;
EOC
;
end of cycle
;
ES
;
Eigenvalue Separation
;
FIMA
;
Fissions per Initial Metal Atom
;
HTR
;
High Temperature Reactor
;
MCB
;
continuous energy Monte Carlo Burnup (code)
;
MCNP
;
Monte Carlo N-Particle (code)
;
MOX
;
Mixed
Oxide
(
fuel
)
;
PWR
;
Pressurized Water Reactor
;
TTA
;
Transmutation Trajectory Analysis
;
UOX
;
Uranium
Oxide
(
fuel
)
;
VVER
;
(Russian) Water-Water Energetic Reactor
刊名:Annals of Nuclear Energy
出版年:2017
2.
Short Communication on “Direct compositional quantification of (U-Th)O
2
- MOX nuclear
fuel
using ns-UV-LIBS and chemometric regression models”
作者:
Manjeet Singh
a
;
Arnab Sarkar
a
;
arnab@barc.gov.in
;
asarkar@ymail.com
;
Xianglei Mao
b
;
Richard E. Russo
b
关键词:
LIBS
;
Chemometrics
;
PLSR
;
Nuclear
fuel
;
AHWR
刊名:Journal of Nuclear Materials
出版年:2017
3.
Characterization of ThO
2
and (Th,U)O
2
pellets consolidated from NSD-sol gel derived nanoparticles
作者:
N. Mohseni
a
;
b
;
S.J. Ahmadi
a
;
sjahmadi@aeoi.org.ir
;
M. Roshanzamir
c
;
M. Najafi
a
;
S.M. Mirvakili
d
关键词:
A. Sol gel Process
;
A.
Fuel
Fabrication
;
B. Nanocrystalline
;
D. ThO2
;
D. (Th
;
U)O2
刊名:Ceramics International
出版年:2017
4.
Feasibility to convert an advanced PWR from UO
2
to a mixed U/ThO
2
core - Part I: Parametric studies
作者:
Jose R. Maiorino
a
;
b
;
joserubens.maiorino@ufabc.edu.br
;
Giovanni Laranjo Stefani
b
;
Joã
;
o M.L. Moreira
a
;
b
;
Pedro C.R. Rossi
a
;
Thiago A. Santos
b
关键词:
Thorium
;
PWR
;
AP1000
;
Neutronics
刊名:Annals of Nuclear Energy
出版年:2017
5.
Oxygen diffusion model of the mixed (U,Pu)O
2 ± x
: Assessment and application
作者:
Emily Moore
a
;
eemevans@gmail.com
;
Christine Gué
;
neau
a
;
Jean-Paul Crocombette
b
刊名:Journal of Nuclear Materials
出版年:2017
6.
Effect of cooling rate on achieving thermodynamic equilibrium in
uranium
-plutonium mixed
oxide
s
作者:
Romain Vauchy
a
;
b
;
romain.vauchy@cea.fr" class="auth_mail" title="E-mail the corresponding author
;
Renaud C. Belin
b
;
Anne-Charlotte Robisson
b
;
Fiqiri Hodaj
c
;
d
关键词:
High temperature X-ray diffraction
;
Thermodynamic equilibrium
;
Phase diagram
;
U&ndash
;
Pu&ndash
O ;
Uranium
;
Plutonium
;
Mixed
oxide
;
Nuclear
fuel
;
MOX
;
Phase separation
;
Miscibility gap
;
Lattice expansion
;
SFR
刊名:Journal of Nuclear Materials
出版年:2016
7.
Synthesis and Characterization of Brannerite Wasteforms for the Immobilization of Mixed
Oxide
Fuel
Residues
作者:
D.J. Bailey
;
dbailey2@sheffield.ac.uk
;
M.C. Stennett
;
N.C. Hyatt
关键词:
Brannerite
;
X-ray diffraction
;
nuclear waste immobilization
;
mixed
oxide
fuel
刊名:Procedia Chemistry
出版年:2016
8.
E-beam and UV induced fabrication of CeO
2
, Eu
2
O
3
and their mixed
oxide
s with UO
2
作者:
Tereza Pavelková
;
a
;
tereza.pavelkova@fjfi.cvut.cz" class="auth_mail" title="E-mail the corresponding author
;
Vojtěch Vaněček
a
;
Ivo Jakubec
b
;
Vá
;
clav Čuba
a
关键词:
E-beam
;
UV
;
Radiation synthesis
;
Nuclear
fuel
s
;
Cerium(IV)
oxide
;
Europium(III)
oxide
;
Uranium
(IV)
oxide
刊名:Radiation Physics and Chemistry
出版年:2016
9.
Used Mixed
Oxide
Fuel
Reprocessing at RT-1 Plant
作者:
Dmitrii Kolupaev
a
;
Michail Logunov
a
;
Alexader Mashkin
a
;
Konstantin Bugrov
a
;
Konstanin Korchenkin
a
;
Andrei Shadrin
b
;
shau@proryv2020.ru
;
Konstanin Dvoeglazov
b
关键词:
mixed U-Pu
oxide
fuel
;
UNF reprocessing
;
hydrometallurgy
刊名:Procedia Chemistry
出版年:2016
10.
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
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