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Chunkuan Shih
Observed names:
C. Shih,
Chun-Kuan Shih,
Chunkuan SHIH,
Shih Chunkuan,
Shih, Chunkuan
Institution:
National Tsing Hua University
Observed institution:
National Tsing Hua University
OpenAlex ID:
A5113573055
Maximizing the cooling capacity and COP of two-stage thermoelectric coolers through genetic algorithm
2005
·
Yi-Hsiang Cheng
, Chunkuan Shih
·
Applied Thermal Engineering
·
91
Introducing PCTRAN as an evaluation tool for nuclear power plant emergency responses
2011
·
Yi-Hsiang Cheng
, Chunkuan Shih
, et al.
·
Annals of Nuclear Energy
·
52
Thermal design investigation of a new tube-type dry-storage system through CFD simulations
2011
·
Yung-Shin Tseng
, Jong-Rong Wang
, et al.
·
Annals of Nuclear Energy
·
44
Development of accident dose consequences simulation software for nuclear emergency response applications
2007
·
Yi-Hsiang Cheng
, Chunkuan Shih
, et al.
·
Annals of Nuclear Energy
·
20
TRACE modeling and its verification using Maanshan PWR start-up tests
2009
·
Jong-Rong Wang
, Hao-Tzu Lin
, et al.
·
Annals of Nuclear Energy
·
18
Model extension and improvement for simulator-based software safety analysis
2006
·
Hui-Wen Huang
, Chunkuan Shih
, et al.
·
Nuclear Engineering and Design
·
17
ATWS analysis for Maanshan PWR using TRACE/SNAP code
2014
·
Che-Hao Chen
, Jong-Rong Wang
, et al.
·
Annals of Nuclear Energy
·
14
Benchmark calculations of pressurizer model for Maanshan nuclear power plant using TRACE code
2009
·
Yi-Hsiang Cheng
, Jong-Rong Wang
, et al.
·
Nuclear Engineering and Design
·
14
Integrated software safety analysis method for digital I&C systems
2008
·
Hui-Wen Huang
, Chunkuan Shih
, et al.
·
Annals of Nuclear Energy
·
14
Optimizing the Arrangement of Two-Stage Thermoelectric Coolers through a Genetic Algorithm
2006
·
Yi-Hsiang CHENG
, Chunkuan SHIH
·
JSME International Journal Series B
·
14
PDF
Investigating the execution of EOPs in LOTDFP + ATWS + LOCA scenarios for an ABWR using MAAP code
2009
·
Yuh-Ming Ferng
, Ying-Ting Liu
, et al.
·
Nuclear Engineering and Design
·
12
1D and Q2D thermal resistance analysis of micro channel structure and flat plate heat pipe
2017
·
Shao-Wen Chen
, Wan-June Chiu
, et al.
·
Microelectronics Reliability
·
10
Station blackout mitigation strategies analysis for Maanshan PWR plant using TRACE
2015
·
Hao-Tzu Lin
, Jong-Rong Wang
, et al.
·
Annals of Nuclear Energy
·
10
The alternate mitigation strategies on the extreme event of the LOCA and the SBO with the TRACE Chinshan BWR4 model
2012
·
Chun-Yu Chen
, Chunkuan Shih
, et al.
·
Nuclear Engineering and Design
·
10
Film Boiling and Vapor Explosions from Small Spheres
1981
·
Chunkuan Shih
, M. M. El-Wakil
·
Nuclear Science and Engineering
·
10
Code crosswalk of Fukushima-like simulations for Chinshan BWR/4 NPP using MELCOR2.1/SNAP, TRACE/SNAP, PCTRAN and MAAP5.03
2017
·
Yu Chiang
, Shao-Wen Chen
, et al.
·
Nuclear Engineering and Design
·
9
Software failure events derivation and analysis by frame-based technique
2007
·
Hui-Wen Huang
, Chunkuan Shih
, et al.
·
Annals of Nuclear Energy
·
9
The establishment of MELCOR/SNAP model of Chinshan nuclear power plant for Ultimate Response Guideline
2016
·
Wen-Sheng Hsu
, Yu Chiang
, et al.
·
Nuclear Engineering and Design
·
7
The development and assessment of TRACE/PARCS model for Lungmen ABWR
2014
·
Hao-Tzu Lin
, Jong-Rong Wang
, et al.
·
Nuclear Engineering and Design
·
7
System-level hazard analysis using the sequence-tree method
2007
·
Hui-Wen Huang
, Chunkuan Shih
, et al.
·
Annals of Nuclear Energy
·
7
Evaluations and Modifications of the EPRI-1 Correlation on PWR Critical Heat Flux Predictions Under Normal and Abnormal Fuel Conditions
1986
·
B. S. Pei
, Y. B. Chen
, et al.
·
Nuclear Technology
·
7
Using genetic algorithms to calibrate the user-defined parameters of IIST model for SBLOCA analysis
2013
·
Chiung-Wen Tsai
, Chunkuan Shih
, et al.
·
Annals of Nuclear Energy
·
6
Improvement of accident dose consequences simulation software for nuclear emergency response applications
2008
·
Yi-Hsiang Cheng
, Chunkuan Shih
, et al.
·
Annals of Nuclear Energy
·
6
LBLOCA analysis for the Maanshan PWR nuclear power plant using TRACE
2012
·
Jung-Hua Yang
, Jong-Rong Wang
, et al.
·
Energy Procedia
·
5
The pressurization transient analysis for Lungmen advanced boiling water reactor using RETRAN-02
2010
·
Chiung-Wen Tsai
, Chunkuan Shih
, et al.
·
Nuclear Engineering and Design
·
5
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Works count:
133
Citation count:
503
H-index:
11
I10-index:
15
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