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反应堆外的辐射场主要是由核供热系统释放的腐蚀产物活化而形成的。为了操作和检修的需要,尽量减少变成辐射源的腐蚀产物是极其重要的。为此研究了日本Inconel 690、国产Inconel 690、Inconel600和Incoloy 800等四种核蒸汽发生器传热管材在模拟核电站一回路介质中静态条件下的均匀腐蚀速率和金属释放速率。结果表明,Inconel 690合金管在一回路介质中具有极低的腐蚀产物释放速率,且试验材料的均匀腐蚀速率和金属释放速率随铬含量的增高而降低。
The radiation field outside the reactor is mainly caused by the activation of the corrosion products released by the nuclear heating system. For operational and service needs, it is extremely important to minimize corrosion products that become radiation sources. For this reason, the uniform corrosion rate and metal release rate of four nuclear steam generator heat transfer tubes, such as Inconel 690, Inconel 690, Inconel 600 and Incoloy 800 in Japan, were simulated under static conditions in the primary circuit of a simulated nuclear power plant. The results show that the Inconel 690 alloy tube has a very low release rate of corrosion products in the primary circuit medium, and the uniform corrosion rate and the metal release rate decrease with the increase of chromium content.