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透射法测量输油管道油垢厚度响应关系的蒙特卡罗模拟 总被引:3,自引:1,他引:2
本文利用蒙特卡罗方法分别计算了中子、γ射线在不同油垢厚度输油管道中的穿透率,建立了油垢厚度与射线计数的响应关系,并分析了中子、γ射线用于输油管道油垢厚度无损检测各自的优缺点. 相似文献
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基于康普顿散射原理,利用蒙特卡罗方法模拟了伽马射线在不同油垢厚度输油管道的散射率,建立了油垢厚度与散射光子计数率的关系。结果表明伽马射线散射法用于管道油垢厚度的无损检测是可行的,其厚度响应比较灵敏。 相似文献
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为改进应用γ射线散射法在原油输运过程中的结垢厚度检测方法,建立一系列模拟实验来研究原油对检测油垢厚度的影响,实验中以石蜡模拟原油。结果表明,在原油厚度小于输油管道内径的三分之一时,随着油垢厚度的改变,散射光子数变化明显,灵敏度较高。在此情况下,用γ射线散射法测量油垢厚度是一可行途径。 相似文献
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γ射线透射法检测输油管道油垢的标定实验研究 总被引:10,自引:0,他引:10
用γ射线透射法对新疆克拉玛依油田φ74mm输油管道油垢的检测进行了标定实验研究,测量了该管道的油垢厚度响应曲线,其结果表示为In(N0/N)=0.00392d—0.00677,并研究了保温层对测量结果的影响。实验装置由^137Csγ放射源和Nal(Tl)闪烁探测器组成。测量结果表明:油垢厚度响应曲线是灵敏的,保温层对测量结果影响不大。 相似文献
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用γ射线透射法测量输油管道油垢的厚度响应 总被引:12,自引:3,他引:9
用γ射线透射法对克拉玛依油田输油管道油垢检测进行了实验研究,测量了油垢的厚度响应,并对测量方法进行了研究,实验测量装置由^137Csγ放射源性和NaI(Tl)闪烁探测器等组成,结果表明:油垢厚度 响应ln(N0/N)=0.00548d-0.0046,油垢厚度响应是灵敏的。 相似文献
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γ射线散射法检测输油管油垢厚度的初步实验研究 总被引:1,自引:0,他引:1
本文用石蜡模拟油垢,用γ射线垂直入射,以一定的散射角接收散射γ光子数,发现散射γ计数与被测石蜡厚度之间存在很好的线性关系.为散射法检测油垢厚度的实验研究奠定了基础. 相似文献
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利用快中子透射法和散射法研究管道口径在62.0mm~126.5mm范围内对测量输油管道油垢厚度响应的影响。实验装置由中子源、中子探测器和微机多道谱仪组成。结果表明:在透射法中,随着管道口径的增加,检测输油管道油垢的灵敏度减小,线性相关系数的平均值为0.993 0,测量精度平均为0.698 4mm。在散射法中,应用指数拟合的结果较好,将数据线性处理,取线性区间,结果显示,随着管道口径增加,线性区间在增大,线性相关系数的平均值为0.958 3,平均测量精度为0.625 7mm。实验结果对进一步开展快中子检测输油管道油垢厚度的研究有一定的指导作用。 相似文献
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含硼钢对慢中子衰减性能的蒙特卡罗模拟 总被引:1,自引:0,他引:1
用MCNP4C程序模拟了日本研制的KTA-304含硼钢对0.025eV、1eV、1keV慢中子衰减吸收性能,并与传统的SUS304钢进行对比。在充分考虑生产加工条件及材料的防腐蚀性、热延性等因素下比较得出,硼浓度在1.13%左右的含硼钢具有较好的慢中子吸收能力,可有效降低次级γ射线效应,在达到辐射防护要求下可减少材料厚度。计算了不同含硼浓度下含硼钢对不同能量慢中子的衰减系数,为中子屏蔽材料的选择提供了合理依据。另外,还考虑了对中子俘获过程中放出γ射线的防护。 相似文献
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《Journal of Nuclear Science and Technology》2013,50(10):865-876
The neutron capture cross sections and capture γ-ray spectra of 147,148,149,150,152,154Sm were measured in the neutron energy region of 10 to 90 keV and at 550 keV. A neutron time-of-flight method was adopted with a 1.5-ns pulsed neutron source by the 7Li(p, n)7Be reaction and with a large anti-Compton NaI(Tl) γ-ray spectrometer. A pulse-height weighting technique was applied to observed capture γ-ray pulse-height spectra to derive capture yields. The capture cross sections were obtained with the error of about 5% by using the standard capture cross sections of 197Au. The present results were compared with the evaluated values of JENDL-3.2 and previous measurements. The capture γ-ray spectra were obtained by unfolding the observed capture γ-ray pulse-height spectra. An anomalous shoulder was clearly observed around 3 MeV in the γ-ray spectra of 150,152,154Sm, and the energy position of the shoulder was consistent with the systematics obtained in our previous work. 相似文献
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《Journal of Nuclear Science and Technology》2013,50(5):421-427
The neutron capture cross sections and capture γ-ray spectra of 167Er were measured in the neutron energy region of 10 to 90keV and at 550 keV. Using a neutron time-of-flight method with a 1.5-ns pulsed neutron source by the 7Li(p, n)7Be reaction, the measurement was performed by detecting prompt γ rays from an enriched capture sample with a large anti-Compton Nal(Tl) spectrometer. A pulse-height weighting technique was applied to observed capture γ-ray pulse-height spectra to extract capture yields. The capture cross sections were derived with the error of about 5% by using the standard capture cross sections of 197Au. The present results were compared with the evaluated values of ENDF/B-VI and the previous measurement. The present measurement at 550 keV was the first one. The capture γ-ray spectra were obtained by unfolding the observed capture γ-ray pulse-height spectra. An anomalous shoulder was clearly observed around 3 MeV in the γ-ray spectra and the energy position of the shoulder was consistent with the systematics obtained in our previous work. The multiplicities of the observed γ rays were derived from the γ-ray spectra. 相似文献
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利用MC法模拟了D-T中子源发出的粒子通过地层元素测井仪内部屏蔽体结构的过程,获得了不同粒子通过不同材料的屏蔽体后能量和核反应截面的分布,从而得出不同材料在不同厚度下的粒子屏蔽效果。模拟结果表明:采用17 cm厚的三层复合屏蔽体结构,所用材料第一层为10 cm厚的钨镍合金,第二层为5 cm厚含20%碳化硼的聚乙烯,第三层为2 cm厚的铅。三层结构对中子的屏蔽率达到98.47%,对γ光子的屏蔽率达到97.68%。可有效降低仪器内部元素干扰,提高分辨率与精确度。 相似文献