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
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Electrochemistry and In Situ Scratch Behavior of 690 Alloy in Simulated Nuclear Power High Temperature High Pressure Water
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图10. 高温高压原位往复划伤过程中电流密度随时间变化 |
Fig.10. Current density changes with elapsed time during high temperature high pressure in situ reciprocating scratches |
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