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1

Kuosheng BWR/6 stability analysis with LAPUR5 code

Hao-Tzu Lin, Jong-Rong Wang, Chang-Lung Hsieh, Chunkuan Shih, Show-Chuyan Chiang, Tong-Li Weng

Journal:

Annals of Nuclear Energy

Year:

2006

Language:

english

File:

PDF, 210 KB

english, 2006

2

In-phase and out-of-phase modes stability analysis with LAPUR5 code for Kuosheng

Jong-Rong Wang, Hao-Tzu Lin, Chunkuan Shih, Chang-Lung Hsieh, Tung-Li Weng, Show-Chyuan Chiang

Journal:

Annals of Nuclear Energy

Year:

2008

Language:

english

File:

PDF, 493 KB

english, 2008

3

TRACE modeling and its verification using Maanshan PWR start-up tests

Jong-Rong Wang, Hao-Tzu Lin, Yi-Hsiang Cheng, Wei-Chen Wang, Chunkuan Shih

Journal:

Annals of Nuclear Energy

Year:

2009

Language:

english

File:

PDF, 1.16 MB

english, 2009

4

Effect of parametric sensitivity on stability boundary of Chinshan NPP

Chang-Lung Hsieh, Jong-Rong Wang, Hao-Tzu Lin, Show-Chuyan Chiang, Tung-Li Weng, Chunkuan Shih

Journal:

Annals of Nuclear Energy

Year:

2009

Language:

english

File:

PDF, 754 KB

english, 2009

5

3RIP trip startup test simulation of TRACE/PARCS model for Lungmen ABWR under different power and flow conditions

Yang, Shu-Ming, Lin, Hao-Tzu, Wang, Jong-Rong, Chen, Hsiung-Chih, Shih, Chunkuan, Chen, Shao-Wen

Journal:

Year:

2015

Language:

english

File:

PDF, 1016 KB

english, 2015

6

1D and Q2D thermal resistance analysis of micro channel structure and flat plate heat pipe

Chen, Shao-Wen, Chiu, Wan-June, Lin, Min-Song, Kuo, Feng-Jiun, Chai, Min-Lun, Lee, Jin-Der, Wang, Jong-Rong, Lin, Hao-Tzu, Lin, Wei-Keng, Shih, Chunkuan

Journal:

Microelectronics Reliability

Year:

2017

Language:

english

File:

PDF, 4.35 MB

english, 2017

7

[ASME 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference - Anaheim, California, USA (Monday 30 July 2012)] Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovatio - TRACE/PARCS Modelling of Feedwater Pump Trip Transients for Lungmen ABWR

Feng, Tsung-Sheng, Lin, Hao-Tzu, Wang, Jong-Rong, Shih, Chunkuan

Year:

2012

Language:

english

File:

PDF, 1.02 MB

english, 2012

8

An investigation of steam–water countercurrent flow model in TRACE

Yi-Hsiang Cheng, Chunkuan Shih, Jong-Rong Wang, Hao-Tzu Lin

Journal:

Annals of Nuclear Energy

Year:

2010

Language:

english

File:

PDF, 772 KB

english, 2010

9

A sensitivity study of BWR instability over global and regional modes at different exposures

Chang-Lung Hsieh, Hao-Tzu Lin, Jong-Rong Wang, Show-Chuyan Chiang, Tung-Li Weng, Chunkuan Shih

Journal:

Nuclear Engineering and Design

Year:

2008

Language:

english

File:

PDF, 937 KB

english, 2008

10

Benchmark calculations of pressurizer model for Maanshan nuclear power plant using TRACE code

Yi-Hsiang Cheng, Jong-Rong Wang, Hao-Tzu Lin, Chunkuan Shih

Journal:

Nuclear Engineering and Design

Year:

2009

Language:

english

File:

PDF, 542 KB

english, 2009

11

Parametric analysis of pressure control system for Lungmen nuclear power plant

Chiung-Wen Tsai, Chunkuan Shih, Jong-Rong Wang, Hao-Tzu Lin, Su-Chin Cheng, Fong-Lun Lin

Journal:

Energy Procedia

Year:

2012

Language:

english

File:

PDF, 311 KB

english, 2012

12

LBLOCA analysis for the Maanshan PWR nuclear power plant using TRACE

Jung-Hua Yang, Jong-Rong Wang, Hao-Tzu Lin, Chunkuan Shih

Journal:

Energy Procedia

Year:

2012

Language:

english

File:

PDF, 321 KB

english, 2012

13

The Turbine Trip without Bypass Analysis for Lungmen ABWR Using TRACE/PARCS

Jong-Rong Wang, Hao-Tzu Lin, Hsiung-Chih Chen, Chunkuan Shih

Journal:

Energy Procedia

Year:

2012

Language:

english

File:

PDF, 405 KB

english, 2012

14

The pressurization transient analysis for Lungmen advanced boiling water reactor using RETRAN-02

Chiung-Wen Tsai, Chunkuan Shih, Jong-Rong Wang, Hao-Tzu Lin, Su-Chin Cheng

Journal:

Nuclear Engineering and Design

Year:

2010

Language:

english

File:

PDF, 1.82 MB

english, 2010

15

The Feedwater Control System and Steam Dump Control System Responses During Large-Load Reduction Transient for Maanshan PWR Plant

Hao-Tzu Lin, Jong-Rong Wang, Chunkuan Shih

Journal:

Procedia Engineering

Year:

2011

Language:

english

File:

PDF, 266 KB

english, 2011

16

The feedwater control system and steam dump control system responses during large-load reduction transient for Maanshan PWR Plant

Hao-Tzu Lin, Jong-Rong Wang, Chunkuan Shih

Journal:

Procedia Engineering

Year:

2011

Language:

english

File:

PDF, 380 KB

english, 2011

17

On study of steam bypass and pressure control system for Lungmen nuclear power plant

Chiung-Wen Tsai, Chunkuan Shih, Jong-Rong Wang, Hao-Tzu Lin, Su-Chin Cheng, Fong-Lun Lin

Journal:

Procedia Engineering

Year:

2011

Language:

english

File:

PDF, 365 KB

english, 2011

18

Assessing the SCRRI and RIP runback performances of TRACE/PARCS for Lungmen ABWR

Chang, Chia-Ying, Feng, Tsung-Sheng, Wang, Jong-Rong, Lin, Hao-Tzu, Shih, Chunkuan

Journal:

Annals of Nuclear Energy

Year:

2014

Language:

english

File:

PDF, 2.27 MB

english, 2014

19

Sensitivity study on the counter-current flow limitation in the DEG LBLOCA with the TRACE code

Chen, Chun-Yu, Shih, Chunkuan, Wang, Jong-Rong, Lin, Hao-Tzu

Journal:

Annals of Nuclear Energy

Year:

2013

Language:

english

File:

PDF, 2.29 MB

english, 2013

20

PSYCHIATRY AND SKIN DISEASE

Lin, Hao-Tzu, Wang, Jong-Rong, Chen, Hsiung-Chih, Shih, Chunkuan

Journal:

Year:

1950

Language:

english

File:

PDF, 401 KB

english, 1950

21

The development and assessment of TRACE/PARCS model for Lungmen ABWR

Lin, Hao-Tzu, Wang, Jong-Rong, Chen, Hsiung-Chih, Shih, Chunkuan

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 3.14 MB

english, 2014

22

Assessment of TRACE CCFL Model with SBLOCA Experiment of IIST Facility

Yang, Jung-Hua, Wang, Jong-Rong, Lin, Hao-Tzu, Shih, Chunkuan

Journal:

Science and Technology of Nuclear Installations

Year:

2012

Language:

english

File:

PDF, 1.52 MB

english, 2012

23

Station blackout mitigation strategies analysis for Maanshan PWR plant using TRACE

Lin, Hao-Tzu, Wang, Jong-Rong, Huang, Kai-Chun, Shih, Chunkuan, Chiang, Show-Chyuan, Liu, Chia-Chuan

Journal:

Annals of Nuclear Energy

Year:

2016

Language:

english

File:

PDF, 5.91 MB

english, 2016

24

[ASME 17th International Conference on Nuclear Engineering - Brussels, Belgium (July 12–16, 2009)] Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance - A Study of Steam-Water Countercurrent Flow Model in TRACE Code

Cheng, Yi-Hsiang, Shih, Chunkuan, Wang, Jong-Rong, Lin, Hao-Tzu

Year:

2009

Language:

english

File:

PDF, 1.19 MB

english, 2009

25

[ASME 2014 22nd International Conference on Nuclear Engineering - Prague, Czech Republic (Monday 7 July 2014)] Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security - Analysis of the Control Rod Drop Accident (CRDA) for Lungmen ABWR

Ho, Ai-Ling, Wang, Jong-Rong, Lin, Hao-Tzu, Shih, Chunkuan

Year:

2014

Language:

english

File:

PDF, 2.46 MB

english, 2014

26

[ASME 2014 22nd International Conference on Nuclear Engineering - Prague, Czech Republic (Monday 7 July 2014)] Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security - Best Estimate Analysis of Maanshan PWR LBLOCA by TRACE Coupling With DAKOTA

Yang, Jung-Hua, Wang, Jong-Rong, Lin, Hao-Tzu, Shih, Chunkuan

Year:

2014

Language:

english

File:

PDF, 997 KB

english, 2014

27

[ASME 2014 22nd International Conference on Nuclear Engineering - Prague, Czech Republic (Monday 7 July 2014)] Volume 2B: Thermal Hydraulics - Modeling and Application of TRACE in the Kuosheng BWR/6 NPP Dry-Storage System

Chiang, Yu, Lin, Hao-Tzu, Wang, Jong-Rong, Chen, Shao-Wen, Tseng, Yung-Shin, Shih, Chunkuan

Year:

2014

Language:

english

File:

PDF, 1.29 MB

english, 2014

28

BWR Parametric Sensitivity Effect of Regional Mode Instability on Stability Boundary

HSIEH, Chang-Lung, LIN, Hao-Tzu, WANG, Jong-Rong, CHIANG, Show-Chuyan, WENG, Tung-Li, SHIH, Chunkuan

Journal:

Journal of Power and Energy Systems

Year:

2008

Language:

english

File:

PDF, 480 KB

english, 2008

29

[ASME 2014 22nd International Conference on Nuclear Engineering - Prague, Czech Republic (Monday 7 July 2014)] Volume 2B: Thermal Hydraulics - The Load Rejection Transient Analysis of Chinshan NPP (BWR/4) Using TRACE/PARCS

Huang, Jhih-Jhong, Chen, Hsiung-Chih, Wang, Jong-Rong, Liao, Lih-Yih, Shih, Chunkuan, Lin, Hao-Tzu

Year:

2014

Language:

english

File:

PDF, 1.86 MB

english, 2014

30

The ultimate response guideline simulation and analysis using TRACE, MAAP5, and FRAPTRAN for the Chinshan Nuclear Power Plant

Wang, Te-Chuan, Wang, Jong-Rong, Lin, Hao-Tzu, Chen, Hsiung-Chih, Chen, Shao-Wen, Shih, Chunkuan, Chiang, Show-Chyuan, Yu, Tzu-Yao

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 2.36 MB

english, 2017

31

[IEEE 2016 5th International Symposium on Next-Generation Electronics (ISNE) - Hsinchu, Taiwan (2016.5.4-2016.5.6)] 2016 5th International Symposium on Next-Generation Electronics (ISNE) - Thermal resistance analysis of micro channel structure with 1D and Q2D methods

Chen, Shao-Wen, Liu, Fang-Chin, Kuo, Feng-Jiun, Chai, Min-Lun, Poh, Cai-Shi, Lee, Jin-Der, Wang, Jong-Rong, Lin, Hao-Tzu, Lin, Wei-Keng, Shih, Chunkuan

Year:

2016

Language:

english

File:

PDF, 522 KB

english, 2016

32

[ASME 16th International Conference on Nuclear Engineering - Orlando, Florida, USA (May 11–15, 2008)] Volume 3: Thermal Hydraulics; Instrumentation and Controls - Benchmark Calculations of Pressurizer Model for Maanshan Nuclear Power Plant Using TRACE Code

Cheng, Yi-Hsiang, Shih, Chunkuan, Wang, Jong-Rong, Lin, Hao-Tzu

Year:

2008

Language:

english

File:

PDF, 1.00 MB

english, 2008

33

[ASME 14th International Conference on Nuclear Engineering - Miami, Florida, USA (July 17–20, 2006)] Volume 2: Thermal Hydraulics - LAPUR5.2 BWR Stability Analysis in Chinshan Nuclear Power Plant

Hsieh, Chang-Lung, Lin, Hao-Tzu, Chiang, Show-Chuyan, Shih, Chunkuan, Wang, Jong-Rong, Weng, Tung-Li

Year:

2006

Language:

english

File:

PDF, 1.07 MB

english, 2006

34

Experimental investigation on local/global void distribution of air-water two-phase flow in a 3Â ÃÂ 3 rod bundle channel under low-flow conditions

Chen, Shao-Wen, Ruan, Pei-Syuan, Lin, Min-Song, Yu, Ya-Chi, Lee, Jin-Der, Yang, Jung-Hua, Lin, Hao-Tzu, Wang, Jong-Rong, Pei, Bau-Shei

Journal:

International Journal of Heat and Fluid Flow

Year:

2020

File:

PDF, 10.17 MB

2020