首页> 外国专利> METHOD FOR ALLEVIATING GENERAL CORROSION OF METAL CONSTITUENT PART IN WATER-COOLING TYPE NUCLEAR REACTOR OR RELATED INSTALLATION AND START OR SPREADING OF CRACK ON SURFACE OF METAL CONSTITUENT PART THEREOF,AND METAL CONSTITUENT PART HAVING OXIDE FILM ON SURFACE THEREOF

METHOD FOR ALLEVIATING GENERAL CORROSION OF METAL CONSTITUENT PART IN WATER-COOLING TYPE NUCLEAR REACTOR OR RELATED INSTALLATION AND START OR SPREADING OF CRACK ON SURFACE OF METAL CONSTITUENT PART THEREOF,AND METAL CONSTITUENT PART HAVING OXIDE FILM ON SURFACE THEREOF

机译:消除水冷式核反应器中金属成分的一般腐蚀的方法或相关的安装,裂纹在金属成分部分表面上的安装或开始以及在金属成分表面上具有氧化膜的金属成分

摘要

PURPOSE: To reduce the start and development of corrosion and crack in a metallic constituent of a water-cooled nuclear reactor or related equipment by injecting the solution of compounds containing non-noble metal into the water of the nuclear reactor. CONSTITUTION: This is a field technique by which the surface of stainless steel or the other metal inside a nuclear reactor is coated or doped with a non-noble metal such as zirconium or titanium. This is carried out by injecting the solution of compounds containing a non-noble metal such as zirconium or titanium into the inside of the high-temperature water of a nuclear reactor. In the nuclear reactor, feed water is fed into the pressure vessel 10 through a feed-water inlet 12 and a feed-water sparger 14. The solution of compounds such as ziroconium is preferably injected at the upstream point of the feed-water inlet 12. The high-temperature inside the core 20 and the radiation of gamma-rays and neutrons act so as to dissolve the compounds such as zirconium. Thus, the ions or atoms of zirconium or the like become free and adhere to the oxide film that coats the surface of stainless steel inside the nuclear reactor.
机译:目的:通过将含有非贵金属的化合物溶液注入核反应堆的水中,以减少水冷核反应堆或相关设备的金属成分中腐蚀和裂纹的发生和发展。宪法:这是一种现场技术,通过该技术,在核反应堆内的不锈钢或其他金属表面涂覆或掺杂了锆或钛等非贵金属。这是通过将含有锆或钛等非贵金属的化合物的溶液注入到核反应堆的高温水中来进行的。在核反应堆中,将进料水通过进水入口12和进水喷雾器14进料到压力容器10中。化合物例如锆的溶液优选在进水入口12的上游点注入。芯20内部的高温以及伽马射线和中子的辐射起着溶解诸如锆之类的化合物的作用。因此,锆等的离子或原子变得自由并附着在覆盖核反应堆内部的不锈钢表面的氧化膜上。

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