核电站用不锈钢在高温高压水中应力腐蚀开裂行为的研究进展

焦洋, 张胜寒, 檀玉

Research Progress on Stress Corrosion Cracking of Stainless Steel for Nuclear Power Plant in High-temperature and High-pressure Water

JIAO Yang, ZHANG Shenghan, TAN Yu

表1 压水堆机组一回路冷却剂系统水质要求

Table 1 Water quality requirements for PWR primary water

Parameter AP1000 Qinshan nuclear power Plant Conductivity 1~40 μS/cm (25 ℃) 1~40 μS/cm (25 ℃) pH 4.2~10.5 (25 ℃) 5.4~10.5 (25 ℃) O2 ≤0.1 mg/L ≤0.1 mg/L Cl- ≤0.15 mg/L ≤0.1 mg/L F- ≤0.15 mg/L --- H2 25~50 cm3 (STP)/kg H2O 25~35 cm3 (STP)/kg H2O Suspended solids ≤0.2 mg/L ≤1.0 mg/L LiOH --- 0.22~2.2 mg/L H3BO3 0~4000 mg/L (calculated as B) 0~2400 mg/L (calculated as B)