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氨型碱性水化学对690TT腐蚀特性的影响 被引量:1

Effect of Ammonia-type Alkaline Water Chemistry on Corrosion of 690TT
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摘要 为探索氨型碱性水化学对传热管材料690TT腐蚀行为的影响,开展传热管材料690TT合金在B-Li-NH_4OH和NH_4OH两种水质下的腐蚀特性研究,分析690TT腐蚀产物释放特性,综合评价氨型碱性水质对690TT腐蚀特性的影响。研究结果表明,690TT材料与两种氨型碱性水质均具有较好的相容性。690TT在两种水质中均形成了致密的氧化膜,氧化膜由NiFe_(2)O_(4)尖晶石氧化物和少量的铁氧化物Fe_(2)O_(3)组成,相对而言690TT在NH_(4)OH型水质条件下的总腐蚀失重量、总腐蚀产物释放量略低于在B-Li-NH_(4)OH水质下,但690TT向水质释放的Ni元素总量与上述规律相反,这可能与Ni元素和氨形成络合物[Ni(NH_(3))_(m)]^(2+)有关,Ni元素释放量增加对反应堆一回路辐照场控制有不利影响。本研究结果可为氨型碱性水化学技术的设计和应用提供数据支撑。 In order to clarify the influence of ammonia-type alkaline water chemistry on the corrosion behaviors of 690TT,the corrosion behavior of 690TT in B-Li-NH_(4)OH and NH_(4)OH solution were studied,the release characteristics of corrosion products from 690TT were analyzed,and the impact of ammonia alkaline solutions on corrosion behavior of 690TT was evaluated comprehensively.The results showed that 690TT was compatible with two kinds of ammonia-type alkaline water chemistry.The surface of 690TT formed dense oxide film,which was composed of NiFe_(2)O_(4)and few Fe_(2)O_(3)oxide film.The weight loss and corrosion releasing of 690TT in NH_(4)OH solution were slightly lower than those in B-Li-NH_(4)OH solution.However,the total amount of Ni released by 690TT was contrary to the results above.It could be related to the formation of[Ni(NH_(3))m]_(2)+complexes between Ni and ammonia.The increasing of Ni releasing had adverse effect on the control of the irradiation field in primary loop in PWR.The results can provide data support for the design and application of ammonia-type alkaline water chemistry.
作者 赵永福 唐敏 姜峨 银朝晖 陈子瑞 张根 吴宗佩 李杨 ZHAO Yongfu;TANG Min;JIANG E;YIN Zhaohui;CHEN Zirui;ZHANG Gen;WU Zongpei;LI Yang(Nuclear Power Institute of China,Chengdu 610213,China)
出处 《材料导报》 EI CAS CSCD 北大核心 2024年第7期167-172,共6页 Materials Reports
基金 中国核动力研究设计院原创基金(YCHJJ17)。
关键词 氨型碱性水化学 镍基合金690TT 腐蚀 ammonia-type alkaline water chemistry Ni-based alloy 690TT corrosion
作者简介 通信作者:赵永福,中国核动力研究设计院反应堆工程研究所副研究员。分别于2009年6月、2012年6月在长沙理工大学获得工学学士学位和硕士学位,毕业后到中国核动力研究设计院反应堆工程研究所工作至今,2021年中国核动力研究设计院核燃料循环与材料专业博士毕业。目前主要从事反应堆冷却剂化学与材料腐蚀、先进缓蚀技术等方面的研究工作。发表核心及以上论文22篇,授权专利标准20项。zhaoyongfu0127@126.com。
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