摘要
对不同理论模型、模型方程及其优缺点等方面进行了综述,结合一回路活化腐蚀产物的迁移特性,推导出一种计算方法,对压水堆一回路管道活化腐蚀产物60Co、58Co的放射性活度进行了评估,通过Pactole计算结果对比论证了该方法的可靠性。
Different theoretical models,model equations,advantages and their disadvantages are reviewed.Combined with the migration characteristics of activated corrosion products in the primary circuit,a calculation method is derived to evaluate the radioactivity of activated corrosion products oCo and 58 Co in the primary circuit of a pressurized water reactor.The reliability of the method is demonstrated by comparing the Pactole calculation results.
作者
李垚
许非
李莉
左伟
吴耀
LI Yao;XU Fei;LI Li;ZUO Wei;WU Yao(China Nuclear Power Research and Design Institute,Chengdu 610005,China;Sichuan Provincial Retired Treatment Engineering Laboratory,Chengdu 610005,China)
出处
《腐蚀与防护》
CAS
CSCD
北大核心
2024年第3期75-79,共5页
Corrosion & Protection
关键词
活化腐蚀产物
压水堆
一回路管道
activated corrosion product
pressurized water reactor
primary circuit pipeline