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从核电站的服役情况看,优化水化学参数是提高其设备寿命最经济有效的方法之一。压水堆一回路冷却剂中加Zn不仅能阻止Ni、Co等在堆芯沉积降低辐射剂量率,同时能降低材料的腐蚀速率以及应力腐蚀开裂(PWSCC)的敏感性。本文通过模拟压水堆核电站一回路的水化学环境下316LN不锈钢的腐蚀实验,研究不同加Zn浓度对材料腐蚀行为的影响,讨论了加Zn后氧化
From the service conditions of nuclear power plants, optimizing the water chemistry parameters is one of the most economical and effective ways to increase the life of equipment. The addition of Zn to the coolant in the PWR primary circuit can not only prevent Ni, Co and other deposition in the core from lowering the radiation dose rate, but also reduce the material corrosion rate and stress corrosion cracking (PWSCC) sensitivity. In this paper, by simulating the corrosion experiment of 316LN stainless steel in the water chemistry environment of the primary circuit of PWR nuclear power plant, the effects of different Zn concentration on corrosion behavior of materials were studied.