Yeh Tsung-kuang | Nuclear Sci. And Technol. Dev. Center National Tsing-hua Univ.
スポンサーリンク
概要
関連著者
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Yeh Tsung-kuang
Nuclear Sci. And Technol. Dev. Center National Tsing-hua Univ.
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Tsai Chuen-horng
Department Of Engineering And System Science National Tsing-hua University
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YEH Tsung-Kuang
Nuclear Science and Technology Development Center, National Tsing-Hua University
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Liu Chang-tong
Nuclear Science And Technology Development Center National Tsing-hua University
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TSAI Chuen-Horng
Department of Engineering and System Science, National Tsing-Hua University
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Wang Mei-ya
Nuclear Science And Technology Development Center National Tsing-hua University
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Wang Bai-yang
Department Of Engineering And System Science National Tsing-hua University
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Yeh T‐k
National Tsing‐hua Univ. Hsinchu Twn
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Yeh Tsung-kuang
Nuclear Science And Technology Development Center National Tsing-hua University
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CHIEN Yuan-Chin
Department of Engineering and System Science, National Tsing-Hua University
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Cheng Yu-hsiang
Department Of Engineering And System Science National Tsing-hua University
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Macdonald Digby
Center For Electrochemical Science And Technology Pennsylvania State University
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Tsai Chuen‐horng
Department Of Engineering And System Science National Tsing-hua University
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LEE Ming-Yong
Department of Engineering and System Science, National Tsing-Hua University
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Lee Ming-yong
Department Of Engineering And System Science National Tsing-hua University
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Yeh Tsung‐kuang
Nuclear Science And Technology Development Center National Tsing-hua University
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CHU Fang
Nuclear Operation Department, Taiwan Power Company
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Chu Fang
Nuclear Operation Department Taiwan Power Company
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Chien Yuan-chin
Department Of Engineering And System Science National Tsing-hua University
著作論文
- The Influence of ZrO_2 Treatment on the Electrochemical Behavior of Oxygen and Hydrogen on Type 304 Stainless Steels in High Temperature Water
- Impact of Power Uprate on the Water Chemistry in the Primary Coolant Circuit of a Boiling Water Reactor Operating under a Fixed Core Flow Rate
- The Influence of Various Treating Parameters on the Corrosion of ZrO_2-Treated Type 304 Stainless Steels in High-Temperature Water
- The Influence of Dissolved Hydrogen on the Corrosion of Type 304 Stainless Steels Treated with Inhibitive Chemicals in High Temperature Pure Water
- Intergranular Stress Corrosion Cracking of Type 304 Stainless Steels Treated with Inhibitive Chemicals in Simulated Boiling Water Reactor Environments
- Intergranular Stress Corrosion Cracking of Platinum Treated Type 304 Stainless Steels in High Temperature Water
- Electrochemical Corrosion Potential Modeling in the Primary Heat Transport Circuit of the Chinshan Boiling Water Reactor under the Condition of Hydrogen Water Chemistry with Noble Metal Coating
- The Efficiency of Noble Metals in Reducing the Corrosion Potential in the Primary Coolant Circuits of Boiling Water Reactors Operating under Hydrogen Water Chemistry Operation