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Yen-Shu Chen
Observed name:
Chen, Yen-Shu
Institution:
National Atomic Research Institute
Observed institutions:
National Tsing Hua University,
Atomic Energy Council,
Institute of Nuclear Energy Research,
National Atomic Research Institute
ORCID:
0000-0002-9868-5225
Observed ORCID:
0000-0002-9868-5225
OpenAlex ID:
A5060426302
Numerical simulation of a heat sink embedded with a vapor chamber and calculation of effective thermal conductivity of a vapor chamber
2008
·
Yen-Shu Chen
, Kuo-Hsiang Chien
, et al.
·
Applied Thermal Engineering
·
79
Analysis of AP1000 containment passive cooling system during a loss-of-coolant accident
2015
·
Zhen-Yu Hung
, Yuh-Ming Ferng
, et al.
·
Annals of Nuclear Energy
·
58
The development of a three-dimensional transient CFD model for predicting cooling ability of spent fuel pools
2012
·
Tzu-Chen Hung
, Vijay K. Dhir
, et al.
·
Applied Thermal Engineering
·
46
A simplified transient three-dimensional model for estimating the thermal performance of the vapor chambers
2006
·
Yen-Shu Chen
, Kuo-Hsiang Chien
, et al.
·
Applied Thermal Engineering
·
38
Investigations of the Thermal Spreading Effects of Rectangular Conduction Plates and Vapor Chamber
2006
·
Yen-Shu Chen
, Kuo-Hsiang Chien
, et al.
·
Journal of Electronic Packaging
·
33
Pressure and temperature analyses using GOTHIC for Mark I containment of the Chinshan Nuclear Power Plant
2011
·
Yen-Shu Chen
, Yng-Ruey Yuann
, et al.
·
Nuclear Engineering and Design
·
25
Thermal analysis for the integrated spent fuel pool of the Chinshan plant in the decommissioning process
2018
·
Yen-Shu Chen
·
Annals of Nuclear Energy
·
20
Lungmen ABWR containment analyses during short-term main steam line break LOCA using GOTHIC
2012
·
Yen-Shu Chen
, Yng-Ruey Yuann
, et al.
·
Nuclear Engineering and Design
·
19
Evaluation of cooling capacity with more fuel stored in the spent fuel pool of the Kuosheng plant
2017
·
Yen-Shu Chen
, Yng-Ruey Yuann
·
Annals of Nuclear Energy
·
16
Accident mitigation for spent fuel storage in the upper pool of a Mark III containment
2016
·
Yen-Shu Chen
, Yng-Ruey Yuann
·
Annals of Nuclear Energy
·
16
Determination of Optimized Rectangular Spreader Thickness for Lower Thermal Spreading Resistance
2009
·
Yen-Shu Chen
, Kuo-Hsiang Chien
, et al.
·
Journal of Electronic Packaging
·
16
Kuosheng Mark III containment analyses using GOTHIC
2013
·
Ansheng Lin
, Yen-Shu Chen
, et al.
·
Nuclear Engineering and Design
·
15
Numerical investigation for the spent fuel storage building design of the Chinshan nuclear plant
2021
·
Bo-Yan Chen
, Yen-Shu Chen
·
Progress in Nuclear Energy
·
12
Negative pressure difference evaluation of Lungmen ABWR containment by using GOTHIC
2014
·
Yen-Shu Chen
, Yng-Ruey Yuann
·
Annals of Nuclear Energy
·
9
Evaluation of the reactor building environmental conditions under a LOCA for the decommissioning Chinshan plant
2021
·
Yen-Shu Chen
, Li-Ying Huang
·
Annals of Nuclear Energy
·
7
Long-term pressure and temperature analysis and suppression pool mixing of Lungmen ABWR containment
2013
·
Yen-Shu Chen
, Yng-Ruey Yuann
·
Annals of Nuclear Energy
·
7
Heat transfer analysis for the temporary spent fuel storage of the Chinshan nuclear plant
2024
·
Bo-Yan Chen
, Yen-Shu Chen
·
Nuclear Engineering and Design
·
6
Short-term pressure and temperature MSLB response analyses for large dry containment of the Maanshan nuclear power station
2014
·
Liang-Che Dai
, Yen-Shu Chen
, et al.
·
Nuclear Engineering and Design
·
5
Thermal analysis for evaluating the required cooling time of the emergency plan exemption for the Maanshan PWR units
2024
·
Yen-Shu Chen
, Bo-Yan Chen
, et al.
·
Progress in Nuclear Energy
·
4
Accident influence to the thermal conditions of the main buildings of the Kuosheng plant during the decommissioning process
2022
·
Ansheng Lin
, Li-Ying Huang
, et al.
·
Nuclear Engineering and Design
·
3
Water Inventory Calculation for the Shutdown Boiling Water Reactors
2022
·
Yen-Shu Chen
, Li-Ying Huang
, et al.
·
Nuclear Engineering and Design
·
2
Fuel integrity evaluation for the shutdown BWR-4 plant during LOCA event
2024
·
Keng-Hsien Hsu
, Liang-Che Dai
, et al.
·
Nuclear Engineering and Design
·
1
Development of a hydrogen diffusion gothic model of MARK III-containment
2015
·
H. Zhen-Yu
, H. Yu-Kai Huang
, et al.
·
Kerntechnik
·
1
Multi-channel GOTHIC model of a postulated spent fuel pool leakage accident for the Maanshan PWR units
2026
·
Yen-Shu Chen
·
Kerntechnik
Thermal-hydraulic analysis of temporary spent fuel storage in the upper pool of the Kuosheng units under postulated leakage accident
2025
·
Yen-Shu Chen
·
Nuclear Engineering and Design
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Works count:
29
Citation count:
438
H-index:
12
I10-index:
13
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