压水堆活化腐蚀产物源项^(58)Co和^(60)Co敏感性研究

Sensitivity of ^(58)Co and ^(60)Co for Activated Corrosion Products Source Terms in Pressurized Water Reactor

以某压水堆核电厂为例,采用CORA程序分析压水堆核电厂一回路材料组成、蒸汽发生器传热管材料钴含量、冷却剂氢氧化锂浓度、净化效率和反应堆运行功率等因素变化对一回路腐蚀产物58Co和60Co活度浓度的影响。计算结果表明:通过限制蒸汽发生器传热管材料中钴元素的含量、提高冷却剂中氢氧化锂浓度、提高冷却剂净化效率和降低功率等措施可以有效降低活化腐蚀产物的活度浓度,为压水堆核电厂辐射剂量控制提供参考。

Taking a pressurized water nuclear power plant as an example, this research uses CORA code to analyze the effect of material construction, the cobalt content of steam generator tubes, purification efficiency, core power and the concentration of LiOH on the corrosion production of 58Co and 60Co in the primary circuit. The results show that these factors can effectively reduce the activity concentration of activated corrosion products sources terms through the control of cobalt content of the steam generator tubes, increasing the concentration of LiOH, improving the coolant purification efficiency and reducing the power level. The research can provide guidance for the radiation dose control of nuclear power plants.