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CNKI学位论文(136)
知网期刊论文(48)
在“
Elsevier电子期刊
”中,
命中:
72
条,耗时:小于0.01 秒
在所有数据库中总计命中:
184
条
1.
Transient
boiling
crisis
induced by heat-load step pulses in a helium vertically heated natural circulation loop with static initial condition
作者:
Herná
;
n Furci
;
hernanfurci@gmail.com" class="auth_mail" title="E-mail the corresponding author
;
Bertrand Baudouy
;
Auré
;
lien Four
关键词:
Boiling
crisis
;
Film
boiling
;
Transient
;
Natural circulation
;
Helium
刊名:International Journal of Heat and Mass Transfer
出版年:2017
2.
Heat transfer and
crisis
phenomena at pool
boiling
of liquid nitrogen on the surfaces with capillary-porous coatings
作者:
A.S. Surtaev
a
;
surtaev@itp.nsc.ru
;
A.N. Pavlenko
a
;
D.V. Kuznetsov
a
;
V.I. Kalita
b
;
D.I. Komlev
b
;
A. Yu. Ivannikov
b
;
A.A. Radyuk
b
关键词:
Boiling
;
Capillary-porous coating
;
Heat transfer enhancement
;
Plasma spraying
;
Critical heat flux
;
Rapid heating
刊名:International Journal of Heat and Mass Transfer
出版年:2017
3.
Numerical simulation of heat transfer and determination of critical heat fluxes at nonsteady heat generation in falling wavy liquid films
作者:
Andrey N. Chernyavskiy
;
cherny@ngs.ru" class="auth_mail" title="E-mail the corresponding author
;
Aleksandr N. Pavlenko
关键词:
Falling liquid films
;
Boiling
expectation
;
Crisis
phenomena
;
Nonsteady heat generation
;
Numerical simulation
刊名:International Journal of Heat and Mass Transfer
出版年:2017
4.
Steady state
boiling
crisis
in a helium vertically heated natural circulation loop - Part 2: Friction pressure drop lessening
作者:
H. Furci
;
hernanfurci@gmail.com" class="auth_mail" title="E-mail the corresponding author
;
B. Baudouy
;
A. Four
;
C. Meuris
关键词:
Helium
;
Boiling
crisis
;
Film
boiling
;
Friction
;
Natural circulation
;
Critical heat flux (CHF)
刊名:Cryogenics
出版年:2016
5.
Steady state
boiling
crisis
in a helium vertically heated natural circulation loop - Part 1: Critical heat flux,
boiling
crisis
onset and hysteresis
作者:
H. Furci
;
hernanfurci@gmail.com" class="auth_mail" title="E-mail the corresponding author
;
B. Baudouy
;
A. Four
;
C. Meuris
关键词:
Helium
;
Boiling
crisis
;
Film
boiling
;
Natural circulation
;
Critical heat flux (CHF)
刊名:Cryogenics
出版年:2016
6.
Droplets
boiling
crisis
of ethanol water solution on duralumin substrate with SiO
2
nanoparticles coating
作者:
S.Y. Misyura
;
misura@itp.nsc.ru" class="auth_mail" title="E-mail the corresponding author
关键词:
Ethanol water solution
;
Droplets
boiling
crisis
;
Nanoparticles ceramic coating
;
Marangoni force
刊名:Experimental Thermal and Fluid Science
出版年:2016
7.
Wall effect on heat transfer
crisis
作者:
S.Y. Misyura
misura@itp.nsc.ru" class="auth_mail" title="E-mail the corresponding author
关键词:
Droplets evaporation
;
Heat flux
;
Heat transfer
crisis
;
Leidenfrost temperature
;
Transitional
boiling
刊名:Experimental Thermal and Fluid Science
出版年:2016
8.
Numerical investigation of the
boiling
crisis
for helical cruciform-shaped rods at high pressures
作者:
Koroush Shirvan
;
kshirvan@mit.edu" class="auth_mail" title="E-mail the corresponding author
关键词:
Boiling
crisis
;
Multiphase flow
;
Nuclear power
;
CFD
刊名:International Journal of Multiphase Flow
出版年:2016
9.
Evaluation of JRC source term methodology using MAAP5 as a fast-running
crisis
tool for a BWR4 Mark I reactor
作者:
M. Vela-Garcí
;
a
;
monica.vela-garcia@ec.europa.eu" class="auth_mail" title="E-mail the corresponding author
;
K. Simola
kaisa.simola@ec.europa.eu" class="auth_mail" title="E-mail the corresponding author
关键词:A ;
activity
;
AC
;
alternating current
;
ASTEC
;
accident source term evaluation code
;
BWR
;
boiling
water reactor is a type of light water nuclear reactor
;
DC
;
direct current
;
DOSE
;
MAAP5 module for the dose calculation
;
ECCS
;
emergency core cooling system
;
EPRI
;
electric power research institute
;
FAI
;
Fauske & Associates
;
LLC is a world leader in nuclear
;
industrial and chemical process safety what developed the MAAP code
;
FASTNET
;
FAST Nuclear Emergency Tools project
;
FASTRUN
;
TG FASTRUN
;
Internat
刊名:Annals of Nuclear Energy
出版年:2016
10.
CFD simulation on critical heat flux of flow
boiling
in IVR-ERVC of a nuclear reactor
作者:
Xiang Zhang
a
;
zhangxiang3@snptc.com.cn" class="auth_mail" title="E-mail the corresponding author
;
Teng Hu
a
;
Deqi Chen
b
;
chendeqi@cqu.edu.cn" class="auth_mail" title="E-mail the corresponding author
;
Yunke Zhong
b
;
Hong Gao
b
关键词:
K. Thermal hydraulics
刊名:Nuclear Engineering and Design
出版年:2016
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