690合金在模拟核电高温高压水中的电化学及原位划伤行为研究
郦晓慧1, 王俭秋2(
), 韩恩厚2, 郭延军1, 郑会3, 杨双亮3
), 韩恩厚2, 郭延军1, 郑会3, 杨双亮3
Electrochemistry and In Situ Scratch Behavior of 690 Alloy in Simulated Nuclear Power High Temperature High Pressure Water
LI Xiaohui1, WANG Jianqiu2(), HAN En-Hou2, GUO Yanjun1, ZHENG Hui3, YANG Shuangliang3
), HAN En-Hou2, GUO Yanjun1, ZHENG Hui3, YANG Shuangliang3
图3. 690合金在高温高压水中的维钝电流密度和温度关系
Fig.3. Relationship between passive current density (ip) and temperature (T) of alloy 690 in high temperature and high pressure water (Ea—apparent activation energy)
