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作 者:崔玉杰 武明亮[1] 张义 牛强 王永仙[1] 郭丽潇[1] 赵伟 崔安熙[1] CUI Yujie;WU Mingliang;ZHANG Yi;NIU Qiang;WANG Yongxian;GUO Lixiao;ZHAO Wei;CUI Anxi(China Institute for Radiation Protection,Taiyuan 030006;Shandong Nuclear Power Co.Ltd.,Shandong Yantai 265116)
机构地区:[1]中国辐射防护研究院,太原030006 [2]山东核电有限公司,山东烟台265116
出 处:《辐射防护》2021年第4期302-308,共7页Radiation Protection
摘 要:AP1000与一般压水堆不同的是其一回路采用注锌加氢技术,使其一回路氧化膜特性发生变化。试验在高压釜中模拟AP1000一回路水化学工况,研究F304L、F316、690三种反应堆主工艺设备材料表面生成的氧化膜特性。结果表明,氧化膜为双层结构,外层氧化膜成分主要是Fe_(2)O_(3)及Fe_(3)O_(4)。F304L不锈钢与F316不锈钢内层氧化膜主要是ZnCr_(2)O_(4),注入的Zn元素取代了FeCr_(2)O_(4)中的铁元素,形成了致密的ZnCr_(2)O_(4)氧化层,内层氧化膜存在少量ZnO和ZnFe_(2)O_(4)。690合金的氧化膜内层为ZnCr_(2)O_(4),同时存在较高含量的ZnO和ZnFe_(2)O_(4)。与前两者不同的是,690合金的氧化膜含少量的二价镍,以NiFe_(2)O_(4)和NiCr_(2)O_(4)形式存在。加锌加氢使得氧化膜更加致密,也明显变薄。The difference between AP1000 and other general PWRs is that its primary loop adopts zinc in-jection and hydrogenation technology,which changes the characteristics of oxide film in the pri-mary loop.The experiment simulates water chemistry condition of AP1000 primary loop in auto-clave to study the characteristics of the oxide film formed on the surface of the three main reactor process equipment materials of F304L,F316,and 690.The results show that the oxide film is a bilayer structure,and the outer oxide film components are mainly Fe_(2)O_(3)and Fe_(3)O_(4).The inner oxide film of F304L and F316 stainless steel is mainly ZnCr_(2)O_(4),and the injected Zn element replaces the iron element in FeCr_(2)O_(4)to form a dense ZnCr_(2)O_(4)oxide layer.A small amount of ZnO and ZnFe_(2)O_(4)is present in the inner oxide film.The inner oxide film of 690 alloy is ZnCr_(2)O_(4),with high content of ZnO and ZnFe_(2)O_(4).Unlike F304L,F316,the oxide film of the 690 alloy contains a small amount of divalent nickel in the form of NiFe_(2)O_(4)and NiCr_(2)O_(4).The addition of zinc and hydrogen makes the oxide film denser and sig-nificantly thinner.
分 类 号:TL944[核科学技术—辐射防护及环境保护]
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