An investigation into the corrosion behaviors of stainless steel and Ni-based alloy in simulated PWR primary water environments

會議論文集

Che Jung Chang, Mei Ya Wang 和 Tsung Kuang Yeh

19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019, 頁碼.442-456

2019

摘要

Dissolved Hydrogen

Pressurized Water Reactor

Primary water stress corrosion cracks

U-Bend Test

1 檢視次數

題名: An investigation into the corrosion behaviors of stainless steel and Ni-based alloy in simulated PWR primary water environments
創作者：: Che Jung Chang - Department of Engineering and System Science, National Tsing Hua University, Hsinchu, Taiwan, Taiwan
Mei Ya Wang - Nuclear Science and Technology Development Center, National Tsing Hua University, Hsinchu, Taiwan, Taiwan
Tsung Kuang Yeh - Department of Engineering and System Science, National Tsing Hua University, Hsinchu, Taiwan, Taiwan
補助款備註: 107A3005EJ; MOST-2221-E-007-074-MY3 / Ministry of Science and Technology and Atomic Energy Council 107A3005EJ / Atomic Energy Council (501100005181) MOST-2221-E-007-074-MY3 / Atomic Energy Council (501100005181)
學術資源類型: 會議論文集
出版日期: 2019
出版資訊: 19th International Conference on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, EnvDeg 2019, 頁碼.442-456
語言: 英語