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Wen-Yu Wang
Wen-Yu Wang
National Kaohsiung University of Science and Technology
在 nkust.edu.tw 的电子邮件经过验证
标题
引用次数
引用次数
年份
Evaluation of crack growth of chloride-induced stress corrosion cracking in dry storage system under different environmental conditions
WY Wang, YS Tseng, TK Yeh
Progress in Nuclear Energy 130, 103534, 2020
52020
Tolerance assessment and crack growth of chloride-induced stress corrosion cracking for Chinshan dry storage system
WY Wang, YS Tseng, TK Yeh
Progress in Nuclear Energy 147, 104210, 2022
42022
Numerical Prediction of the Aerodynamics and Aeroacoustics of a 25 kW Horizontal Axis Wind Turbine
WY Wang, YM Ferng
Journal of Mechanics, ufae024, 2024
2024
Numerical model for noise reduction of small vertical-axis wind turbines
WY Wang, YM Ferng
Wind Energy Science 9 (3), 651-664, 2024
2024
A Study of Wind Energy around Urban High-Rise Buildings of Different Turbulence Models
WY Wang
Proceedings of 2023 International Conference on Mechatronic, Automobile, and …, 2023
2023
小型水平軸風機數值模擬計算與驗證分析
王文豫
台灣機電工程國際學會第九屆全國學術研討會, 2023
2023
Numerically Evaluate Hydrated Residual Water Drying Process for Dry Storage System under Low Thermal Load Situation
MHW Wen-Yu Wang, Yung-Shin Tseng, Chin-Hung Lin, Yuh-Ming Ferng
The 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics …, 2022
2022
Chloride-Induced Stress Corrosion Cracking Crack Growth Rate of Stainless Steel Canister for Concrete Cask under Marine Condition
TKY Wen-Yu Wang, Yung-Shin Tseng
The 13th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics …, 2022
2022
Spent Nuclear Fuel Heatup Calculations Supporting Emergency Planning Exemption Using CFD Code
WY Wang, YS Tseng, CH Lin, TK Yeh
Nuclear Technology 208 (7), 1165-1183, 2022
2022
Development of 3-D numerical methodology to investigate transient characteristics of fuel temperature and hydrated residual water during drying process of dry storage system
YS Tseng, WY Wang, CH Lin, YM Ferng, MH Wan
Annals of Nuclear Energy 172, 109083, 2022
2022
The RESRAD code applications for radiological safety analysis of nuclear power plants decommissioning
HE Hsieh, HF Miao, WY Wang, YC Liu, BS Pei
Transactions of the American Nuclear Society, 2019
2019
Radiological safety assessment of decommissioning nuclear power plants using the RESRAD code
WY Wang, HE Hsieh, YC Liu, BS Pei
The Proceedings of the International Conference on Nuclear Engineering …, 2019
2019
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