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CNKI会议论文(2)
CNKI学位论文(11)
知网期刊论文(21)
在“
Elsevier电子期刊
”中,
命中:
65
条,耗时:0.0229859 秒
在所有数据库中总计命中:
34
条
1.
Radiological dose assessment for the
hypothetical
severe
accident
of the Tehran Research Reactor and corresponding emergency response
作者:
Rohollah Ahangari
;
rahangarishahdehi@gmail.com" class="auth_mail" title="E-mail the corresponding author
;
Omid Noori-Kalkhoran
;
Nahid Sadeghi
关键词:
Radiological dose assessment
;
Severe
hypothetical
accident
;
Protective actions
刊名:Annals of Nuclear Energy
出版年:2017
2.
Investigation of a Hydrogen Mitigation System During Large Break Loss-Of-Coolant
Accident
for a Two-Loop Pressurized Water Reactor
作者:
Mehdi Dehjourian
a
;
Reza Sayareh
b
;
Mohammad Rahgoshay
a
;
m.rahgoshay@gmail.com" class="auth_mail" title="E-mail the corresponding author
;
Gholamreza Jahanfarnia
a
;
Amir Saied Shirani
c
关键词:
Core Concrete Interaction
;
Loss of Coolant
Accident
;
MELCOR
;
Passive Autocatalytic Recombiner
;
Pressurized Water Reactor
;
Severe
Accident
刊名:Nuclear Engineering and Technology
出版年:2016
3.
Integrity analysis of a reactor pressure vessel subjected to a realistic pressurized thermal shock considering the cooling plume and constraint effects
作者:
V.F. Gonzá
;
lez-Albuixech
a
;
vicente.gonzalez@psi.ch" class="auth_mail" title="E-mail the corresponding author
;
G. Qian
a
;
guian.qian@psi.ch" class="auth_mail" title="E-mail the corresponding author
;
M. Sharabi
a
;
b
;
M. Niffenegger
a
;
B. Niceno
a
;
N. Lafferty
a
关键词:
Pressurized thermal shock
;
Reactor pressure vessel
;
Constraint loss
;
Fracture mechanics
;
Computational fluid dynamics
刊名:Engineering Fracture Mechanics
出版年:2016
4.
Feasibility of shock attenuation by simple obstacles in mitigating
severe
accident
explosive loads
作者:
Jong-Woon Park
;
parkjw@dongguk.ac.kr" class="auth_mail
;
Jin-Su Kim
关键词:
Fukushima
;
Severe
accident
;
Explosion
;
Shock wave
;
Attenuation
;
Obstacle
刊名:Annals of Nuclear Energy
出版年:August, 2014
5.
Simulation and dose analysis of a
hypothetical
accident
in Sanmen nuclear power plant
作者:
Yangmo Zhu
;
Jianghua Guo
;
Chu Nie
;
Youhua Zhou
关键词:
Lagrangian particle dispersion model
;
Flexpart
;
Nuclear
accident
;
Nuclide dispersion
;
Dose analysis
刊名:Annals of Nuclear Energy
出版年:March, 2014
6.
Estimation of radionuclide transport to reactor containment building under unprotected
severe
accident
scenario in SFR
作者:
Arjun Pradeep
;
P. Mangarjuna Rao
;
pmr@igcar.gov.in" class="auth_mail
;
mangarjun@gmail.com" class="auth_mail
;
B.K. Nashine
;
P. Selvaraj
;
P. Chellapandi
关键词:
Radionuclide transport
;
Fission product inventory
;
Sodium cooled fast reactor
;
Hypothetical
core disruptive
accident
;
Reactor containment building
刊名:Progress in Nuclear Energy
出版年:July 2014
7.
Atmospheric dispersion modeling and radiological safety analysis for a
hypothetical
accident
of Ghana Research Reactor-1 (GHARR-1)
作者:
J.L. Muswema
a
;
jeremiemuswem@yahoo.fr" class="auth_mail
;
E.O. Darko
b
;
J.K. Gbadago
c
;
E.K. Boafo
c
关键词:
Atmospheric dispersion modeling
;
Source term
;
MCNPX
;
HotSpot
刊名:Annals of Nuclear Energy
出版年:June, 2014
8.
Source term evaluation of two loop PWR under
hypothetical
severe
accident
s
作者:
Khurram Mehboob
;
khurramhrbeu@gmail.com
;
Cao Xinrong
caoxinrong@hrbeu.edu.cn
关键词:
Pressurized water reactor
;
Source term
;
Severe
accident
;
Containment response
;
Station black out
;
Loss of coolant
刊名:Annals of Nuclear Energy
出版年:2012
9.
Application of safety analysis code SIMMER-IV to blockage
accident
s in FASTEF subcritical core
作者:
V. Kriventsev
;
A. Rineiski
;
W. Maschek
关键词:
Fast reactor
;
Lead&ndash
;
Bismuth Eutectic
;
Safety analysis
;
Unprotected blockage
刊名:Annals of Nuclear Energy
出版年:February, 2014
10.
Analysis on criticality properties and control strategies after reflooding of a damaged reactor core
作者:
Hae Sun Jeong
a
;
haesunin@kaeri.re.kr" class="auth_mail
;
Chang Je Park
b
;
Kwang Soon Ha
a
关键词:
Reactor corium
;
Re-criticality
;
Critical mass
;
Void reactivity
;
Boron control
刊名:Annals of Nuclear Energy
出版年:July, 2014
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