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Elsevier电子期刊(463)
在“
Elsevier电子期刊
”中,
命中:
463
条,耗时:小于0.01 秒
在所有数据库中总计命中:
463
条
1.
RELAP5
MOD3.2 modification and application to the transient analysis of a fluoride-salt-cooled high-temperature reactor
作者:
Limin Liu
;
Dalin Zhang
;
dlzhang@mail.xjtu.edu.cn
;
Qiqi Yan
;
Rongshuan Xu
;
Chenglong Wang
;
Suizheng Qiu
;
G.H. Su
关键词:
FHR
;
RELAP5
modification
;
Thermo-physical properties
;
Fluoride salts
;
Transient analysis
刊名:Annals of Nuclear Energy
出版年:2017
2.
Simulation of the in-vessel retention device heat-removal capability of AP-1000 during a core meltdown accident
作者:
Fei-Jan Tsai
a
;
fealane@yahoo.com" class="auth_mail" title="E-mail the corresponding author
;
Min Lee
a
;
mlee@ess.nthu.edu.tw" class="auth_mail" title="E-mail the corresponding author
;
Hsiang Chun Liu
b
关键词:
In-vessel retention
;
AP-1000
;
CHF
;
RELAP5
-3D
;
KAIST
刊名:Annals of Nuclear Energy
出版年:2017
3.
Experimental and computational simulation of thermal stratification in large pools with immersed condenser
作者:
Sunil Kumar
a
;
ksunil86.in@gmail.com
;
P.K. Vijayan
a
;
b
;
vijayanp@barc.gov.in
;
Umasankari Kannan
a
;
c
;
Manish Sharma
b
;
D.S. Pilkhwal
b
关键词:
Passive decay heat removal
;
Gravity Driven Water Pool (GDWP)
;
Thermal stratification
;
Isolation Condenser (IC) performance
;
RELAP5
/MOD 3.2
刊名:Applied Thermal Engineering
出版年:2017
4.
Performance-based ECCS cladding acceptance criteria: A new simulation approach
作者:
A. Zoino
a
;
angelo@zoino.it" class="auth_mail" title="E-mail the corresponding author
;
A. Alfonsi
b
;
andrea.alfonsi@inl.gov" class="auth_mail" title="E-mail the corresponding author
;
C. Rabiti
b
;
cristian.rabiti@inl.gov" class="auth_mail" title="E-mail the corresponding author
;
R.H. Szilard
b
;
ronaldo.szilard@inl.gov" class="auth_mail" title="E-mail the corresponding author
;
F. Giannetti
a
;
fabio.giannetti@uniroma1.it" class="auth_mail" title="E-mail the corresponding author
;
G. Caruso
a
;
gianfranco.caruso@uniroma1.it" class="auth_mail" title="E-mail the corresponding author
关键词:
LOCA
;
ECCS
;
Acceptance criteria
;
Cladding design
;
RAVEN
;
PHISICS
;
RELAP5
-3D
刊名:Annals of Nuclear Energy
出版年:2017
5.
Coupled simulations of the NACIE facility using
RELAP5
and ANSYS FLUENT codes
作者:
Daniele Martelli
a
;
daniele.martelli@ing.unipi.it
;
Nicola Forgione
a
;
Gianluca Barone
a
;
Ivan di Piazza
b
刊名:Annals of Nuclear Energy
出版年:2017
6.
Approaches to modelling a solar field for direct generation of industrial steam
作者:
Roger Cundapí
;
a
;
Sara L. Moya
a
;
Loreto Valenzuela
b
;
loreto.valenzuela@psa.es
关键词:
Solar thermal energy
;
Parabolic troughs
;
Industrial process heat
;
Direct steam generation
;
RELAP5
刊名:Renewable Energy
出版年:2017
7.
Control system design and validation platform development for small pressurized water reactors (SPWR) by coupling an engineering simulator and MATLAB/Simulink
作者:
Peiwei Sun
a
;
sunpeiwei@xjtu.edu.cn
;
Huanhuan Zhao
a
;
Longtao Liao
b
;
Jianmin Zhang
a
;
Guanghui Su
a
关键词:
Small pressurized water reactor
;
Control system design
;
Numerical simulation
;
Thermal-hydraulic modeling
;
Engineering simulator
刊名:Annals of Nuclear Energy
出版年:2017
8.
Loss of Coolant Accident in Pressurized Water Reactor. Prediction of a 6-inch Cold Leg Break with
Relap5
and Cathare 2
作者:
Michał Pawluczyk
;
Piotr Mazgaj
;
Sebastian Gurgacz
;
Michał Gatkowski
;
Piotr Darnowski
;
michal.pawluczyk@itc.pw.edu.pl" class="auth_mail" title="E-mail the corresponding author
关键词:
RELAP5
;
CATHARE2
;
PWR
;
IB-LOCA
;
Nuclear Safety
刊名:Procedia Engineering
出版年:2016
9.
Validation of
RELAP5
/MOD3.3 for subcooled boiling, flashing and condensation in a vertical annulus
作者:
William D. Fullmer
a
;
Vineet Kumar
b
;
Caleb S. Brooks
b
;
csbrooks@illinois.edu" class="auth_mail" title="E-mail the corresponding author
关键词:
RELAP5
;
Subcooled boiling
;
Flashing
;
Condensation
;
Validation
刊名:Progress in Nuclear Energy
出版年:2016
10.
Improvement and validation of the wall heat transfer package of
RELAP5
/MOD3.3
作者:
Pan Wu
;
Xiaofei Xiong
;
Jianqiang Shan
;
jqshan@mail.xjtu.edu.cn
;
Junli Gou
;
Bin Zhang
;
Bo Zhang
关键词:
RELAP5
/MOD3.3
;
Modified wall heat transfer package
;
Code validation
刊名:Nuclear Engineering and Design
出版年:2016
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