核废物桶检测中探测效率的数值方法

为了既准确又快速地进行探测效率刻度,针对中低放射性废物活度测量,提出了一种基于探测对象、准直器和以高纯锗探测器为例的空间分布的探测效率实时数值计算方法.采用该方法对不同位置、不同能量的点放射源进行效率刻度,与蒙特卡罗方法计算结果的相对偏差均在5%以内.使用γ射线探测系统对木材和聚氨酯填充的废物桶样品进行实验测量,得到核素137Cs和60Co的探测效率,相同工况下的数值计算结果与实验测量值的相对误差均在12%以内,且多数小于5%.研究结果表明,在进行放射性核废物桶检测时,采用该数值计算方法可以快速而准确地进行效率刻度.

Numerical Method of Detection Efficiency for adioactive Waste Drum Detections Detections

bstract： In order to calibrate detection efficiency fast and accurately, a real time numerical method was proposed for measuring radiation of low and medium radioactive waste based on the spatial distribution of detect objects, collimator, and taking the HPGe detector as an example. This method can calculate detection efficiency of point source with different locations and energies, and the relative deviations are less than 5% by comparing with the results of Monte Carlo calculation. The γ ray detection system was used to measure waste drum samples of wood and polyurethane with 137Cs and 60Co nuclides, and the relative errors between numerical calculation and experimental measurement were within 12%, and most of them were less than 5%. Thus, this numerical calculation method can be used as an accurate and quick calibration of detection efficiency for radioactive waste drum detection.