基于高純鍺探測器的核電廠一回路系統(tǒng)輻射源項就地γ譜測量
發(fā)布時間:2018-07-16 17:00
【摘要】:針對核電廠一回路系統(tǒng)管道內壁沉積的腐蝕活化產物,開展γ輻射源項就地測量技術研究;诟呒冩N探測器開發(fā)了輻射源項就地測量系統(tǒng)(Sterm-HPGe),利用蒙特卡羅軟件進行了無源效率刻度,并開展了實驗室效率驗證工作。在300~1 408 ke V能量范圍內,HPGe探測器在無準直器屏蔽和有準直器屏蔽情況下,點源全能峰效率計算值與測量值的相對偏差分別在±5%和±10%以內。測量系統(tǒng)在我國壓水堆核電廠進行了現(xiàn)場應用,能夠較準確地測量出管道內60Co、58Co、110mAg等典型沉積核素的源項活度,管道表面劑量率的計算值與測量值的相對偏差一般在±40%以內。
[Abstract]:The in-situ measurement of 緯 -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 鹵5% and 鹵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 鹵40%.
【作者單位】: 中國輻射防護研究院;中國原子能科學研究院;
【分類號】:R144
[Abstract]:The in-situ measurement of 緯 -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 鹵5% and 鹵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 鹵40%.
【作者單位】: 中國輻射防護研究院;中國原子能科學研究院;
【分類號】:R144
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