摘要
活化腐蚀产物是压水堆核电厂运行期间的重要辐射源。但由于其产生和迁移过程的复杂性,目前很难建立精确的机理模型进行准确计算。本研究从反应堆堆芯设计、结构材料使用、水化学、机组运行等方面分析了“华龙一号”和CPR1000机组的相似性和可参考性,以CPR1000系列核电厂近年来48个循环的冷却剂活化腐蚀产物运行数据为基础,经研究分析给出了“华龙一号”机组压水堆活化腐蚀产物的稳态现实源项和设计源项,并和三代压水堆EPR、AP1000的源项进行了对比,分析了方法及结果的合理性。
Activated corrosion products are important radiation sources during the normal operation of nuclear power plants.However,it is difficult to predict the activities of the activated corrosion products by theoretical simulation due to the complexity of the migration process.In this study,one method based on the measured radiochemical data of its predecessors have been developed by comparing the similarity between HPR1000 and CPR1000 in respect of core design,the use of structural material,water chemistry and operation mode.Based on the operation data of coolant activated corrosion products in 48 cycles of CPR1000,the realistic source term and design source term of activated corrosion products of HPR1000 at steady state have been determined.In addition,the results have also been compared with other third-generation PWR,which proves the rationality of the analysis method.
作者
王奇
WANG Qi(Hualong Nuclear Power Technology Co.,Ltd.Beijing 100037,China)
出处
《核科学与工程》
CAS
CSCD
北大核心
2022年第5期1125-1132,共8页
Nuclear Science and Engineering
