Chunkuan Shih

National Tsing Hua University — Taiwan

Engineering · Physical Sciences

11h-index473citations109works0.02yr avg
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Research Topics

Nuclear Engineering Thermal-Hydraulics(70), Nuclear reactor physics and engineering(67), Nuclear Materials and Properties(23), Nuclear and radioactivity studies(19), Risk and Safety Analysis(15)

Publications109 total

The establishment of analysis methodology of NRCDose3 for Kuosheng nuclear power plant decommissioning
Kerntechnik·2022
Analysis of Air-Water Two-Phase Flow in a 3x3 Rod Bundle
Zenodo (CERN European Organization for Nuclear Research)·2020· 1 citedOpen Access
Feasibility study for dispersed bubbly flow and other flow patterns spectrum boundary by probability density function
2018
Analysis of transient pressure and temperature variations in a subcooled boiling channel under forced vertical excitations
2018· 1 cited
Application of electrical impedance on measurement of voidfraction in two-phaseflow
2018
Module Characteristics and Performance Analysis of Thermoelectric Generators
International Journal of Electronics and Electrical Engineering·2018
The study of the mitigation strategy of Lungmen ABWR nuclear power plant using RELAP5 and FRAPTRAN with the interface SNAP
Annals of Nuclear Energy·2017
Code crosswalk of Fukushima-like simulations for Chinshan BWR/4 NPP using MELCOR2.1/SNAP, TRACE/SNAP, PCTRAN and MAAP5.03
Nuclear Engineering and Design·2017· 9 cited
1D and Q2D thermal resistance analysis of micro channel structure and flat plate heat pipe
Microelectronics Reliability·2017· 10 cited
The ultimate response guideline simulation and analysis using TRACE, MAAP5, and FRAPTRAN for the Chinshan Nuclear Power Plant
Annals of Nuclear Energy·2017· 3 cited
Modeling Fukushima Dose Consequences with EPZDose
2017· 1 cited
The Establishment and Simulation of TRACE/FRAPTRAN/MELCOR/SNAP Model for Chinshan Nuclear Power Plant Ultimate Response Guideline
2017· 1 cited
The establishment of MELCOR/SNAP model of Chinshan nuclear power plant for Ultimate Response Guideline
Nuclear Engineering and Design·2016· 7 cited
Application of non-intrusive conductance sensors to local measurement of two-phase flow
2016
Analysis of characteristics and performance of thermoelectric modules
2016· 4 cited
Thermal resistance analysis of micro channel structure with 1D and Q2D methods
2016
The Establishment and Application of TRACE/CFD Model for Maanshan PWR Nuclear Power Plant
2016Open Access
3RIP trip startup test simulation of TRACE/PARCS model for Lungmen ABWR under different power and flow conditions
Kerntechnik·2015
Station blackout mitigation strategies analysis for Maanshan PWR plant using TRACE
Annals of Nuclear Energy·2015· 10 cited
Implementation and Assessment of Moody Homogeneous Equilibrium Critical Flow Model of RELAP5-3D
Nuclear Science and Engineering·2015
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Frequent Co-authors

Jong-Rong Wang(30), Hao-Tzu Lin(20), Yi-Hsiang Cheng(14), Hui-Wen Huang(6), Ming‐Huei Chen(6), Shao-Wen Chen(6), Swu Yih(5), Show-Chyuan Chiang(4), Hsiung-Chih Chen(4), Chiung-Wen Tsai(4), Chang-Lung Hsieh(4), Tung-Li Weng(3), Tong-Li Weng(3), Tingyi Wang(3), Su-Chin Cheng(3), Show-Chuyan Chiang(3), Shaoshih Ma(3), Yng-Ruey Yuann(3), Sow-Chyuang Jiang(2), Min-Lun Chai(2)