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内部出版物
CNKI学位论文(109)
知网期刊论文(151)
在“
Elsevier电子期刊
”中,
命中:
46
条,耗时:0.1049577 秒
在所有数据库中总计命中:
260
条
1.
Dynamic rod
worth
simulation study for a sodium-cooled TRU burner
作者:
Sang Ji Kim
;
Pham Nhu Viet Ha
;
phamha@kaeri.re.kr" class="auth_mail" title="E-mail the corresponding author
;
hapnv0915@gmail.com" class="auth_mail" title="E-mail the corresponding author
;
Min Jae Lee
;
Chang Mu Kang
刊名:Nuclear Engineering and Design
出版年:2015
2.
Effects of high density dispersion fuel loading on the
control
rod
worth
of a low enriched uranium fueled material test research reactor
作者:
Farhan Muhammad
;
farhan73@hotmail.com
关键词:
MTR
;
WIMS
;
CITATION
;
Control
rod
worth
;
High density fuels
刊名:Annals of Nuclear Energy
出版年:2013
3.
Development of a
control
rod depletion methodology for the Westinghouse NEXUS system
作者:
Fausto Franceschini
;
Baocheng Zhang
;
Larry Mayhue
;
Erwin M¨¹ller
;
Petri Forslund Guimar?es
关键词:
NEXUS
;
Control
rod depletion
;
Pin power recovery
刊名:Progress in Nuclear Energy
出版年:2013
4.
Calculation of
control
rod
worth
and temperature reactivity coefficient of fuel and coolant with burn-up changes for VVRS-2 MWth nuclear reactor
作者:
Mohammad Rahgoshay
a
;
M.rahgoshay@gmail.com
;
Omid Noori-Kalkhoran
b
;
1
;
o_noori@yahoo.com
刊名:Nuclear Engineering and Design
出版年:2013
5.
Monte Carlo simulation of additional safety
control
rod for commercial MNSR to enhance safety
作者:
Y.V. Ibrahim
a
;
yakubviva@yahoo.com
;
H.C. Odoi
b
;
R.L. Njinga
c
;
M.O. Adeleye
d
;
S.A. Jonah
a
关键词:
Control
rod
worth
;
Excess reactivity
;
Shutdown margin
;
HEU
;
LEU
;
MNSR
刊名:Annals of Nuclear Energy
出版年:2012
6.
Benchmarking of the WIMSD/CITATION deterministic code system for the neutronic calculations of TRIGA Mark-III research reactors
作者:
E. Amin
;
A. Shama
;
H. Hussein
关键词:
Neutronic calculations
;
Reactor physics
;
TRIGA
;
WIMSD-5B
;
WIMSD-IAEA
;
TRX
;
BAPL benchmark lattices
刊名:Annals of Nuclear Energy
出版年:April, 2014
7.
Comparing neutronics codes performance in analyzing a fresh-fuelled research reactor core
作者:
P. Savva
;
M. Varvayanni
;
A.C. Fern
;
es
;
J.G. Marques
;
N. Catsaros
关键词:
Neutronic codes
;
Monte Carlo codes
;
Deterministic codes
;
MCNP
;
TRIPOLI
;
XSDRN
刊名:Annals of Nuclear Energy
出版年:January, 2014
8.
Neutronic analysis of a gaseous
control
system for the HTR-10 reactor
作者:
S.A. Hosseini
;
hosseiniabhari@ut.ac.ir
关键词:
Gaseous
control
system
;
HTR-10
;
PBMR
;
Axial flux
;
Differential reactivity
;
Reactivity
worth
刊名:Annals of Nuclear Energy
出版年:2012
9.
Core design improvement by optimizing the
control
and protection system elements distribution
作者:
Amir Hosein Fadaei
;
Mohammad Mehdi Fadaei
;
Shabnam Kia
;
Saeed Setayeshi
关键词:
CPS optimization
;
Control
rods
;
Neural network
;
Simulated annealing
;
CPS
worth
;
Core design
刊名:Annals of Nuclear Energy
出版年:2010
10.
Simulation of start-up measurements with the KIKO3D code and its application for determining the scram rod
worth
uncertainty in the VVER-440 reactor
作者:
Gy. Hegyi
;
a
;
ghegyi@aeki.kfki.hu
;
A. Keresztú
;
ri
a
;
Cs. Mará
;
czy
a
;
G. Hordó
;
sy
a
;
E. Temesvá
;
ri
a
关键词:
Scram reactivity
;
Differential
control
rod
worth
;
Reactor kinetic code
;
Signal of the ex-core detector
刊名:Annals of Nuclear Energy
出版年:2011
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