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Te-Chuan Wang
Institution:
National Atomic Research Institute
Observed institutions:
Chung Yuan Christian University,
National Tsing Hua University,
Atomic Energy Council,
Institute of Nuclear Energy Research,
National Atomic Research Institute
ORCID:
0000-0002-5917-0317
Observed ORCID:
0000-0002-5917-0317
OpenAlex ID:
A5086272024
Deep learning schemes for event identification and signal reconstruction in nuclear power plants with sensor faults
2021
·
Ting-Han Lin
, Te-Chuan Wang
, et al.
·
Annals of Nuclear Energy
·
32
Comparison of Severe Accident Results among SCDAP/RELAP5, MAAP, and MELCOR Codes
2005
·
Te-Chuan Wang
, Shih-Jen Wang
, et al.
·
Nuclear Technology
·
19
Analysis of Severe Accident Management Strategy for a BWR-4 Nuclear Power Plant
2005
·
Te-Chuan Wang
, Shih-Jen Wang
, et al.
·
Nuclear Technology
·
12
Effectiveness of the Raw-Water System as a Severe-Accident-Management Measure in Station Blackout Accidents
2006
·
Te-Chuan Wang
, Shih-Jen Wang
, et al.
·
Nuclear Technology
·
8
On-site simulator-based initiating event detection and identification in NPPs
2022
·
Guan-Wen Chen
, Huey-Chii Liang
, et al.
·
Progress in Nuclear Energy
·
7
Numerical investigation on the influence of the type of PI controller combined with MAAP code on the steady-state performance of a nuclear power plant
2019
·
Cheng-Lun Yu
, Te-Chuan Wang
, et al.
·
Nuclear Engineering and Design
·
7
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
RPV Depressurization Strategy Analysis for Chinshan Nuclear Power Plant by Using MAAP5
2016
·
Yu-Huai Shih
, Te-Chuan Wang
·
Nuclear Technology
·
7
Localization and size estimation for breaks in nuclear power plants
2021
·
Ting-Han Lin
, Ching Chen
, et al.
·
Nuclear Engineering and Technology
·
5
PDF
Simulation of a PWR Reactor Vessel Level Indicating System during Station Blackout with MELCOR 1.8.5
2006
·
Te-Chuan Wang
, Shih-Jen Wang
, et al.
·
Nuclear Technology
·
5
Analysis of Kuosheng Station Blackout Accident Using MELCOR 1.8.4
2000
·
Shih-Jen Wang
, Chien-Sheng Chien
, et al.
·
Nuclear Technology
·
5
Analysis of Kuosheng Large-Break Loss-of-Coolant Accident with MELCOR 1.8.4
2000
·
Te-Chuan Wang
, Shih-Jen Wang
, et al.
·
Nuclear Technology
·
5
Melcor Self-Initialization Algorithm for Pressurized Water Reactors and Its Importance in Accident Analysis
1997
·
Chun-Sheng Chien
, Shih-Jen Wang
, et al.
·
Nuclear Technology
·
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
Uncertainty Quantification Using the MAAP5 Code of In-Vessel Hydrogen Generation in a Severe Accident at an Advanced Boiling Water Reactor
2019
·
Te-Chuan Wang
, Min Lee
·
Nuclear Technology
·
4
An Investigation of FLEX Implementation in Maanshan NPP by Using MAAP 5
2017
·
Bo-Bin Xiao
, Te-Chuan Wang
·
Springer eBooks
·
4
A real-time computer graphical user interface for Advanced Boiling Water Reactor case comparison using MAAP software
2010
·
Yu-Chen Chen
, Yuan-Hsiang Chang
, et al.
·
International Computer Symposium
·
4
Simulation of Maanshan TMLB’ Sequence with MELCOR 1.8.3
1999
·
Shih-Jen Wang
, Chun-Sheng Chien
, et al.
·
Nuclear Technology
·
4
The ultimate response guideline simulation and analysis using TRACE, MAAP5, and FRAPTRAN for the Chinshan Nuclear Power Plant
2017
·
Te-Chuan Wang
, Jong-Rong Wang
, et al.
·
Annals of Nuclear Energy
·
3
Numerical Study on Pi Controller Combined With Maap Code for Simulating the Steady-state Core Flow of a Nuclear Power Plant
2019
·
Cheng-Lun Yu
, Te-Chuan Wang
, et al.
·
The Proceedings of the International Conference on Nuclear Engineering (ICONE)
·
2
Mitigating medium break loss of coolant accidents: Optimizing control system setpoints using genetic algorithms
2025
·
Wei-Shen Hsu
, Yu-Min Chen
, et al.
·
Progress in Nuclear Energy
·
1
Validation of EPG/SAG Rev. 4 of the Kuosheng Nuclear Power Plant Using the MAAP5 Code
2024
·
Yu-Min Chen
, Te-Chuan Wang
, et al.
·
Nuclear Technology
·
1
The Establishment and Simulation of TRACE/FRAPTRAN/MELCOR/SNAP Model for Chinshan Nuclear Power Plant Ultimate Response Guideline
2017
·
Chunkuan Shih
, Jong-Rong Wang
, et al.
·
Springer eBooks
·
1
Comparison of Severe Accident Results by Using MAAP5 and MAAP4 Codes
2010
·
Te-Chuan Wang
·
The Proceedings of the International Conference on Nuclear Engineering (ICONE)
·
1
An Advanced Boiling Water Reactor Monitoring System Using Modular Accident Analysis Program and Computer Graphical User Interface
2008
·
Yuan-Hsiang Chang
, Mu-Ping Xu
, et al.
·
Nuclear Technology
·
1
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Works count:
29
Citation count:
154
H-index:
7
I10-index:
3
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