【作者】 温菊花； 姜峨； 刘金华； 夏小娇； 龚宾；

【Author】 WEN Ju-hua;JIANG E;LIU Jin-hua;XIA Xiao-jiao;GONG Bin;Nuclear Power Institute of China;

【机构】 中国核动力研究设计院；

【摘要】 针对大型压水堆一回路冷却剂富集¹⁰B的硼锂水化学,进行了300℃条件下锂硼水化学计算。选取pH_300℃作为一回路冷却剂计算依据和控制指标,根据压水堆冷却剂化学平衡和物料平衡,对不同富集度的硼锂水化学进行计算,并绘制了40%富集度硼-锂协调控制曲线。结果表明,富集10B的硼锂水化学,降低了硼含量提高了pH,¹⁰B富集度在40%以上能维持堆芯运行于pH为7.2～7.4。通过燃料包壳材料Zirlo合金和主管道材料316 L不锈钢在pH为7.2～7.4富集¹⁰B的硼锂水化学条件下的高温腐蚀性能试验结果表明,富集¹⁰B的硼锂水化学条件下两种材料均匀腐蚀速率较低,未产生局部腐蚀,材料与冷却剂水化学均有良好的相容性。更多还原

【Abstract】 Based on the primary water chemistry enriched ¹⁰B, the calculation of water chemistry contained lithium and boron at the temperature of 300 ℃ was carried out. Based on the pH300 ℃ as a calculation ground and control index, the calculation of water chemistry at different concentration of boron was carried out, the coordinated control curve of lithium and boron for 40% enrichment was obtained, according to the chemical equilibrium and material balance for the coolant of pressurized water reactor. The calculation results show that the use EBA of 40% enrichment, can reduce the initial concentration of boron and improve the primary coolant pH value, enabling the core of reactor to operate at pH300 ℃ 7.2 to 7.4. Properties of high temperature corrosion of fuel cladding material（Zirlo alloy） and main vessel material（316 L stainless steel） in the primary water chemistry enriched ¹⁰B were investigated by using autoclave. The test results show that that the general corrosion rates of both Zirlo alloy and 316 L stainless steel are very low, and there is no evidence of local corrosion, so materials have good compatibility with the water chemistry enriched ¹⁰B conditions.更多还原