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Chou, Hsoung-Wei
24  Ergebnisse:
Personensuche X
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1

Applicability investigation on failure assessment diagram o..:

Chou, Hsoung-Wei ; Yu, Jiun-Shya ; Huang, Chin-Cheng
International Journal of Pressure Vessels and Piping.  209 (2024)  - p. 105180 , 2024
Link: https://doi.org/10.1016/..
 
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2

The structural and non–linear dynamic analysis for radioact..:

Shen, Yu-Yu ; Cheng, Kuei-Jen ; Chou, Hsoung-Wei
Nuclear Engineering and Technology.  55 (2023)  8 - p. 3010-3016 , 2023
Link: https://doi.org/10.1016/..
 
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3

International case survey and literature review of maintena..:

Lin, Sue-Ray ; Chou, Hsoung-Wei ; Chen, Jien-Jong
International Journal of Pressure Vessels and Piping.  198 (2022)  - p. 104654 , 2022
Link: https://doi.org/10.1016/..
 
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4

Stress intensity factor assessment for reactor pressure ves..:

Lee, Chih-Hsuan ; Chou, Hsoung-Wei
Engineering Fracture Mechanics.  275 (2022)  - p. 108838 , 2022
Link: https://doi.org/10.1016/..
 
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5

Probabilistic fracture analysis for boiling water reactor v..:

Chou, Hsoung-Wei ; Chang, Ching-Hsin
Annals of Nuclear Energy.  167 (2022)  - p. 108827 , 2022
Link: https://doi.org/10.1016/..
 
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6

Application of Flaw Updating Process on Probabilistic Integ..:

Chou, Hsoung-Wei ; Huang, Pin-Chiun ; Ferng, Yuh-Ming
Nuclear Technology.  207 (2020)  5 - p. 735-749 , 2020
Link: https://doi.org/10.1080/..
 
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7

Development of pressure-temperature operation limits for a ..:

Chou, Hsoung-Wei ; Shen, Yu-Yu ; Huang, Chin-Cheng
International Journal of Pressure Vessels and Piping.  179 (2020)  - p. 103944 , 2020
Link: https://doi.org/10.1016/..
 
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8

Demonstration of Structural Integrity of Boiling Water Reac..:

Chou, Hsoung-Wei ; Huang, Chin-Cheng ; Huang, Pin-Chiun.
Nuclear Technology.  206 (2020)  12 - p. 1919-1931 , 2020
Link: https://doi.org/10.1080/..
 
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9

Large thermal gradients on structural integrity of a reacto..:

Huang, Pin-Chiun ; Chou, Hsoung-Wei ; Ferng, Yuh-Ming.
International Journal of Pressure Vessels and Piping.  179 (2020)  - p. 103942 , 2020
Link: https://doi.org/10.1016/..
 
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10

Development and application of safety assessment system in ..:

Chang, Ching-Hsin ; Chou, Hsoung-Wei ; Huang, Chin-Cheng
International Journal of Pressure Vessels and Piping.  167 (2018)  - p. 43-51 , 2018
Link: https://doi.org/10.1016/..
 
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11

Comparison of ASME pressure–temperature limits on the fract..:

Chou, Hsoung-Wei ; Huang, Chin-Cheng
Annals of Nuclear Energy.  108 (2017)  - p. 366-375 , 2017
Link: https://doi.org/10.1016/..
 
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12

Probabilistic ageing and risk analysis tools for nuclear pi..:

Qian, Guian ; Chou, Hsoung-Wei ; Niffenegger, Markus.
Nuclear Engineering and Design.  300 (2016)  - p. 541-551 , 2016
Link: https://doi.org/10.1016/..
 
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13

The influence of chemistry concentration on the fracture ri..:

Huang, Pin-Chiun ; Chou, Hsoung-Wei ; Ferng, Yuh-Ming
Nuclear Engineering and Design.  297 (2016)  - p. 188-196 , 2016
Link: https://doi.org/10.1016/..
 
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14

Fracture risk assessment for the pressurized water reactor ..:

Chou, Hsoung-Wei ; Huang, Chin-Cheng
Nuclear Engineering and Design.  300 (2016)  - p. 412-421 , 2016
Link: https://doi.org/10.1016/..
 
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15

Probabilistic Structural Integrity Analysis of Boiling Wate..:

Chou, Hsoung-Wei ; Huang, Chin-Cheng
International Journal of Nuclear Energy.  2015 (2015)  - p. 1-9 , 2015
Link: https://doi.org/10.1155/..
 
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