摘要
采用蒙特卡罗无源刻度的方法建立了2 m^3废物钢箱效率刻度模型,计算了溴化镧探测器的能量与道址关系,以及全能峰的效率曲线,模拟计算了能量区间在100~1500 keV探测效率,并根据能量刻度结果和效率刻度结果,对某核电分拣废物的主要核素的识别,并对其放射性活度浓度进行了测量。结果表明,废物包中主要核素为58Co、60Co、154Eu、95Nb等,废物包的放射性活度浓度为低放射性废物。
The 2 m^3 waste steel box model was established by using the Monte Carlo passive scale method,the relationship between the energy and the road site of the lanthanum bromide detector was calculated,and the efficiency curve of the omnipotent peak was calculated.The detection efficiency of the peak was calculated by simulating different positions and the energy range was 100~1500 keV.According to the scale results,the major nuclides in anuclear power waste sorting were indentified,and the radioactivity concentration of it was measured.As a result,the main nuclides in the waste steel box were 58Co,60Co,154Eu,95Nb,etc.,and the activity concentration was low-level radioactive waste.
作者
寇子琦
李绪平
朱晨晨
KOU Zi-qi;LI Xu-ping;ZHU Chen-chen(The Second Branch of 404 Co.,Ltd.,Gansu Lanzhou 732850,China)
出处
《广州化工》
CAS
2020年第18期104-106,共3页
GuangZhou Chemical Industry
关键词
无源效率刻度
溴化镧探测器
废物分拣
passive efficiency calibration
lanthanum bromide detector
waste sorting