典型压水堆运行工况下活化腐蚀产物及剂量率计算分析

Analysis of the Activated Corrosion Products and Dose Rate in a Typical PWR Under Operation Condition

压水堆很大一部分的职业照射剂量来自于非辐照区管壁与冷却剂接触时沉积的活化腐蚀产物。为计算典型核电厂主回路中活化腐蚀产物产生的辐射场,本文建立基于浓度差驱动原理的活化腐蚀产物迁移模型模拟了典型核电厂运行3 165天由主回路结构材料产生的活化腐蚀产物,并计算其对职业照射的贡献。计算结果表明反应堆运行期间短寿命核素60Com是放射性活度的主要贡献者,但58Co、60Co等长寿命核素却是剂量率的主要来源。而停堆后,短寿命核素迅速衰变消失,长寿命核素成为放射性活度及剂量率的主要来源。

In PWR plant,most occupational radiation exposure(ORE)of personnel is due to contaminated out-flux walls by activated corrosion products(ACPs)in contact with the primary coolant.Purpose:In order to simulate the ACPs along the primary circuit in a typical PWR,in the paper,the ACPs from structure materials in a typical PWR operating for 3165 days is simulated,and then the ORE produced by the ACPs is calculated.The results show the short-lived nuclides 60mCo contributes most to the ACPs,but 58Co,60Co become the main contributors to the dose rate.While after shutdown,the short-lived nuclides decay out,the long-lived nuclides become main source of radioactivity and dose rate.