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Ru‐Feng Liu
Observed names:
Liu Ru-feng,
R.F. LIU,
R.F. Liu,
Ru Feng Liu,
Ru-Feng Liu,
Ru‐feng Liu
show all 6
Institution:
National Atomic Research Institute
Observed institutions:
National Taipei University of Technology,
National Taiwan Ocean University,
PLA Rocket Force University of Engineering,
Institute of Nuclear Energy Research,
National Atomic Research Institute,
Taiyuan University of Technology,
National Cheng Kung University
show all 7
ORCID:
0000-0001-8065-2348
Observed ORCID:
0000-0001-8065-2348
OpenAlex ID:
A5057376912
Microstructure evolution and mechanical properties of B4C/6061Al neutron absorber composite sheets fabricated by powder metallurgy
2017
·
H.S. Chen
, W.X. Wang
, et al.
·
Journal of Alloys and Compounds
·
100
Helicopter H∞ control design with robust flying quality
2003
·
Chi-Chung Luo
, Ru-Feng Liu
, et al.
·
Aerospace Science and Technology
·
70
Finite element analyses of the effect of weld overlay sizing on residual stresses of the dissimilar metal weld in PWRs
2020
·
Ru-Feng Liu
, Jong-Chang Wang
·
Nuclear Engineering and Design
·
23
Welding residual stress analysis for weld overlay on a BWR feedwater nozzle
2012
·
Ru-Feng Liu
, Chin-Cheng Huang
·
Nuclear Engineering and Design
·
20
Applications of the direct Trefftz boundary element method to the free-vibration problem of a membrane
2002
·
Jiang Ren Chang
, Ru Feng Liu
, et al.
·
The Journal of the Acoustical Society of America
·
19
An asymmetric indirect Trefftz method for solving free-vibration problems
2003
·
J.R. Chang
, R.F. Liu
·
Journal of Sound and Vibration
·
17
Application of finite element method to effect of weld overlay residual stress on probability of piping failure
2022
·
Ru-Feng Liu
, Jong-Chang Wang
·
International Journal of Pressure Vessels and Piping
·
16
Application of symmetric indirect Trefftz method to free vibration problems in 2D
2003
·
Jiang‐ren Chang
, Ru‐feng Liu
, et al.
·
International Journal for Numerical Methods in Engineering
·
15
Probabilistic fracture analysis for boiling water reactor pressure vessels subjected to low temperature over-pressure event
2012
·
Chin-Cheng Huang
, Hsoung-Wei Chou
, et al.
·
Annals of Nuclear Energy
·
14
Structural integrity analyses for preemptive weld overlay on the dissimilar metal weld of a pressurizer nozzle
2011
·
Chin-Cheng Huang
, Ru-Feng Liu
·
International Journal of Pressure Vessels and Piping
·
14
Safety aspects of spent fuel management in nuclear power plants during transition to decommissioning
2020
·
Ru-Feng Liu
, Chia-Kuan Chen
, et al.
·
Annals of Nuclear Energy
·
12
Corrosion fatigue behavior of dissimilar metal weldments under nominal constant ΔK loading mode in a simulated BWR coolant environment
2011
·
J.Y. Huang
, R.F. Liu
, et al.
·
Corrosion Science
·
10
Indirect T‐Trefftz and F‐Trefftz methods for solving boundary value problem of Poisson equation
2006
·
Ru‐Feng Liu
, Weichung Yeih
, et al.
·
Journal of the Chinese Institute of Engineers
·
8
Weld Residual Stress Analysis and the Effects of Structural Overlay on Various Nuclear Power Plant Nozzles
2012
·
Tao Zhang
, Frederick W. Brust
, et al.
·
Journal of Pressure Vessel Technology
·
7
Reactor pressure vessel integrity assessment by probabilistic fracture mechanics – A plant specific analysis
2013
·
Bo-Yi Chen
, Chin-Cheng Huang
, et al.
·
International Journal of Pressure Vessels and Piping
·
5
Influence on structure and fracture mechanics evaluations of a BWR feedwater nozzle following weld overlay repair
2023
·
Ru-Feng Liu
, Ming-Chung Young
·
Journal of Mechanics
·
4
PDF
The Influence of Chemistry Concentration Uncertainty on the Probabilistic Fracture Mechanics Analysis
2011
·
Bo-Yi Chen
, Chin-Cheng Huang
, et al.
·
ASME Pressure Vessels and Piping Conference (PVP)
·
3
Verification Study of Probabilistic Fracture Mechanics Analysis Code for Reactor Pressure Vessel During Pressurized Thermal Shock
2022
·
Ru-Feng Liu
·
International Journal of Mechanical Engineering and Applications
·
2
PDF
A fast searching algorithm for real-time sound source localization
2017
·
Chen-Hsuan Jung
, Ru-Feng Liu
, et al.
·
Annual Conference of the Society of Instrument and Control Engineers of Japan (SICE)
·
2
Probabilistic Fracture Analysis for Boiling Water Reactor Pressure Vessels Subjected to Low Temperature Over-Pressure Event
2010
·
Hsoung-Wei Chou
, Chin-Cheng Huang
, et al.
·
ASME Pressure Vessels and Piping Conference (PVP)
·
2
Boiling Water Reactor Pressure Vessel Integrity Evaluation by Probabilistic Fracture Mechanics
2010
·
Bo-Yi Chen
, Chin-Cheng Huang
, et al.
·
ASME Pressure Vessels and Piping Conference (PVP)
·
2
Weld Residual Stress Analysis and the Effects of Structural Overlay on Various Nuclear Power Plant Nozzles
2010
·
Tao Zhang
, Bud Brust
, et al.
·
ASME Pressure Vessels and Piping Conference (PVP)
·
2
Execution experience of spent nuclear fuel dry storage projects in Taiwan
2026
·
Chih-Hao Chen
, Ru-Feng Liu
·
Nuclear Engineering and Technology
·
1
Probabilistic mechanical assessment of ABWR feedwater piping to identify fractures using plant-specific parameters
2025
·
Ru-Feng Liu
·
International Journal of Pressure Vessels and Piping
·
1
Application of Probabilistic Fracture Mechanics Analysis on BWR Recirculation Piping Systems
2016
·
Yu-Yu Shen
, Hsoung-Wei Chou
, et al.
·
ASME Pressure Vessels and Piping Conference (PVP)
·
1
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Works count:
33
Citation count:
375
H-index:
11
I10-index:
12
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