本文推导了一套反应堆冷却剂腐蚀产物比活性的计算公式,进行了计算分析,验证了国外有关参考数据;并在此基础上提出“一般压水型核动力装置中堆内部件不锈钢的钻含量最好小于0.02%;堆外一回路不锈钢部件的钴含量可以不加特殊限制要求”的观点。这种观点的成立,将可能在满足辐射安全要求的前提下降低堆外一回路不锈钢部件的建造成本(对每一中小型装置来说,可节省3—20万元),并可简化生产工艺。 In this paper, a set of formulas for calculating the specific activity of reactor coolant corrosion products are deduced, and the calculation and analysis are carried out to verify the relevant reference data abroad. On the basis of this, the authors put forward “the drilling content of stainless steel in reactor components in a general pressurized water nuclear power plant Preferably less than 0.02%; the cobalt content of the stainless steel parts outside the reactor can be specified without any special restrictions ”. The establishment of this view will probably reduce the cost of constructing the stainless steel components of the primary loop of the reactor (which can save between RMB 300,000 and RMB 200,000 for each small and medium sized unit) while meeting the radiation safety requirements and simplifying the production process .