基于高纯锗探测器的核电厂一回路系统辐射源项就地γ谱测量
发布时间：2018-07-16 17:00
【摘要】：针对核电厂一回路系统管道内壁沉积的腐蚀活化产物,开展γ辐射源项就地测量技术研究。基于高纯锗探测器开发了辐射源项就地测量系统(Sterm-HPGe),利用蒙特卡罗软件进行了无源效率刻度,并开展了实验室效率验证工作。在300~1 408 ke V能量范围内,HPGe探测器在无准直器屏蔽和有准直器屏蔽情况下,点源全能峰效率计算值与测量值的相对偏差分别在±5%和±10%以内。测量系统在我国压水堆核电厂进行了现场应用,能够较准确地测量出管道内60Co、58Co、110mAg等典型沉积核素的源项活度,管道表面剂量率的计算值与测量值的相对偏差一般在±40%以内。
[Abstract]:The in-situ measurement of 纬 -radiation source term was carried out for the corrosion activated products of pipeline inner wall deposition in primary circuit system of nuclear power plant. Based on the high purity germanium detector, a radiation source in-situ measurement system (Sterm-HPGe) was developed. The passive efficiency calibration was carried out by Monte Carlo software, and the laboratory efficiency verification was carried out. In the energy range of 1 408ke V, the relative deviation between the calculated peak efficiency of point source and the measured value is within 卤5% and 卤10%, respectively, in the case of no collimator shielding and collimator shielding. The measurement system has been applied in the field of PWR nuclear power plant in China. It can accurately measure the source activity of typical deposited nuclides such as 60CoN58CoHN 110mAg in the pipeline. The relative deviation between the calculated value of the surface dose rate of the pipeline and the measured value is generally within 卤40%.
【作者单位】： 中国辐射防护研究院;中国原子能科学研究院;
【分类号】：R144
[Abstract]:The in-situ measurement of 纬 -radiation source term was carried out for the corrosion activated products of pipeline inner wall deposition in primary circuit system of nuclear power plant. Based on the high purity germanium detector, a radiation source in-situ measurement system (Sterm-HPGe) was developed. The passive efficiency calibration was carried out by Monte Carlo software, and the laboratory efficiency verification was carried out. In the energy range of 1 408ke V, the relative deviation between the calculated peak efficiency of point source and the measured value is within 卤5% and 卤10%, respectively, in the case of no collimator shielding and collimator shielding. The measurement system has been applied in the field of PWR nuclear power plant in China. It can accurately measure the source activity of typical deposited nuclides such as 60CoN58CoHN 110mAg in the pipeline. The relative deviation between the calculated value of the surface dose rate of the pipeline and the measured value is generally within 卤40%.
【作者单位】： 中国辐射防护研究院;中国原子能科学研究院;
【分类号】：R144
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