摘要
探讨了Am-Be中子源替代^(252)Cf活化燃料棒,利用多探测器串列测定燃料棒内芯块^(235)U丰度及硼涂覆层厚度的可行性.模拟计算结果表明,使用Am-Be中子源对燃料棒活化后,使用BGO探测器串列对活化后燃料棒内芯块缓发γ射线强度进行测量,可以达到目前^(252)Cf中子源检测设备同等性能指标.设备可方便设计为双通道,提高检测效率.若采用单通道设计,还可降低Am-Be中子源活度.
The feasibility of using Am-Be neutron source instead of^(252)Cf activated fuel rod to measure the enrichment of^(235)U and the thickness of boron coating of pellets in the fuel rod by using multi-detector tandem was discussed.The simulation calculation results show that:after using the Am-Be neutron source to activate the fuel rod,the BGO detector tandem is used to measure the delayedγ-ray intensity of the activated fuel rod inner pellet,which can reach the same performance as the current^(252)Cf neutron source measurement equipment.The equipment can be designed as a dual channel to improve detection efficiency conveniently.If a single-channel design is adopted,the activity of the Am-Be neutron source can be reduced.
作者
王长虹
刘明
张雷
汪陆
马金波
黄少川
WANG Chang-hong;LIU Ming;ZHANG Lei;WANG Lu;MA Jin-bo;HUANG Shao-chuan(China Nuclear Power Engineering Co,Ltd Zhengzhou Branch,Zhengzhou 450052,China)
出处
《核电子学与探测技术》
CAS
北大核心
2022年第5期924-928,共5页
Nuclear Electronics & Detection Technology