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作 者:邱绍宇[1] 苏兴万[1] 文燕[1] 闫福广 喻应华[1] 何艳春[1]
机构地区:[1]中国核动力研究设计院
出 处:《核动力工程》1995年第4期336-341,共6页Nuclear Power Engineering
摘 要:采用适合高Cr含量合金的晶间腐蚀试验方法(沸腾65%HNO。+0.1%HF溶夜浸渍试验)和在316℃、50%NaOH溶液中的慢应变速率试验(SSRT).研究了热处理对690合金晶间腐蚀和碱应力腐蚀性能的影响.热处理包括不同固溶温度(950-1150℃)及特殊热处理(T.T715℃)时不同保持时间(2~30h),根据试验结果.推荐69O合金的热处理条件是;固溶温度应<1100℃,在715℃特殊热处理保持时间15h。Alloy 690 is a new high chromium nickel base alloy that is promising as an advanced steam generator tubing materials. Authors have studied on the effect of heat treamtment on the corrosion resistance of alloy 690. Test materials were treated at 715℃ for 2~30 hours after final annealing at low temperature such as 950℃ to high temperature such as 1150℃.From the view point of the intergranular corrosion in the boiling solution of 65% HNO3+ 0. 1 % HF and the stress corrosion cracking(SCC) resistance in 50 NaOH solution, the following heat treatment condition is considered to be optium for alloy 690. The mill annealing temperature is less 1100℃, thermal treatment 715℃ for 15 hours.
分 类 号:TG151.1[金属学及工艺—热处理] TG174.3[金属学及工艺—金属学]
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