加锌对690合金在高温水中氧化膜的影响

来源 :中国原子能科学研究院年报 | 被引量 : 0次 | 上传用户:weaseltrick
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向反应堆冷却剂中加锌,可减缓停堆大修期间核电站的辐射场强度,也可改变核电站结构氧化膜的特性,从而减缓结构材料在压水堆环境中的腐蚀,并且抑制结构材料应力腐蚀裂纹的萌生和扩展,我国目前正在引进、消化、吸收的第3代AP1000核电站,也采用加锌技术改善水化学环境。在轻水反应堆中,镍基合金600和690被广泛的用作结构材料,本文在国内首次开展加锌对核电结构材料氧化膜影响的动水回路实验,采用SEM-EDS、XPS等分析测试方法,研究了在模拟大型先 Adding zinc to the reactor coolant can reduce the radiation field strength of nuclear power plants during shutdown and overhaul, and can also change the characteristics of the oxide films of nuclear power plants so as to slow down the corrosion of structural materials in PWR environments and to suppress the stress corrosion cracking of structural materials The initiation and expansion of China’s third-generation AP1000 nuclear power station, which is currently being introduced, digested and absorbed, also uses zinc plus technology to improve the water chemistry environment. In light water reactors, Ni-based alloys 600 and 690 are widely used as structural materials. In this paper, the first hydrodynamic circuit experiment was conducted in China for the effects of zinc addition on the oxide film of nuclear structural materials. SEM-EDS and XPS , Studied in the simulation of large first
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