Bae Byung-Joon, Han Jeoh, Hong Jongsup, Hur Do-Haeng
Materials Safety Technology Development Division, Korea Atomic Energy Research Institute, Daejeon 34057, Korea.
Division of Mechanical Engineering, Yonsei University, Seoul 03722, Korea.
Materials (Basel). 2021 Oct 28;14(21):6460. doi: 10.3390/ma14216460.
The purpose of this work was to examine the effect of tensile stress on the oxide properties of a nickel-based Alloy 600 that was exposed to simulated nuclear steam generator water at 340 °C for 1000 h. The size of the outer oxide particles increased, and the chromium content of the inner oxides decreased under tensile stress. Electrochemical measurements revealed that the charge carrier density increased, and the charge transfer resistance and film resistance were reduced under the tensile stress condition. These changes in the oxide properties are attributed to the formation of short diffusion paths such as line and surface defects due to tensile deformation.
这项工作的目的是研究拉伸应力对镍基合金600氧化物性能的影响，该合金在340°C的模拟核蒸汽发生器水中暴露1000小时。在拉伸应力作用下，外层氧化物颗粒尺寸增大，内层氧化物的铬含量降低。电化学测量表明，在拉伸应力条件下，载流子密度增加，电荷转移电阻和膜电阻降低。氧化物性能的这些变化归因于拉伸变形导致的线缺陷和表面缺陷等短扩散路径的形成。
