摘要
介绍了压水堆核电站堆芯燃料和冷却剂中 1 4C和 3H产生量的计算方法 ,计算了田湾核电站每年在堆芯燃料和冷却剂中产生的 1 4C和 3H的总活度 ,将该计算结果与俄罗斯在田湾核电站最终安全分析报告中给出的数据进行了比较分析 ,并从减少这两种核素产生量的角度提出了一些设计建议。
The method of calculating the potential annual yields of 14 C and 3H in fuel and coolant in reactor core of PWR NPPs is given. The annual yields of the two nuclides in the fuel and coolant in reactor core of Tianwan NPP are calculated and compared with the data given in FSAR of Tianwan NPP on part of Russia. Some suggestions to design are presented in order to decrease the annual yields of 14 C and 3H.
出处
《辐射防护通讯》
2004年第3期23-26,共4页
Radiation Protection Bulletin
