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FULL-ENERGY PEAK EFFICIENCY OF ASYMMETRICAL POLYHEDRON GERMANIUM DETECTOR

机译:不对称多面体锗探测器的全能峰效率

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To understand the nuclear structure for most elements, it is essential to investigate the nuclear excitations by using high precision gamma-ray spectroscopy in which intensive measurements should be carried out. This is becoming a new challenge for the radiation scientific community nowadays, where the instrumentations and technical advances must be developed to be used in a wide range of applications. To discover the weakest nuclear reaction, the maximum probability of the detection system of the total energy of any released individual photon must be determined. In this work, a new mathematical method to calculate the absolute full-energy peak efficiency of asymmetrical polyhedron germanium detector is presented. This type of detector can be arranged in array, forming "complex detectors of encapsulated germanium crystals", with the solid angle reaching 82 % of total solid angle coverage, i.e., with the highest possible efficiency and with a good quality of spectral response. In addition, the photon path length was enclosed in the mathematical method to determine its attenuation through different materials such as, the detector active medium and any other material in-between source-detector system during the measuring process. The comparison between the efficiency calculated in this work and that of the published Monte Carlo simulation showed a good agreement and a small variation. However, the method discussed in the current work can be useful in nuclear safeguards, in overcoming the huge difficulties in identification of the energy range of radioactive isotopes and their quantities in nuclear waste.
机译:要了解大多数元素的核结构,必须使用高精度的伽马射线能谱来研究核激发,在其中应进行大量测量。对于当今的辐射科学界而言,这已成为新的挑战,在辐射科学界中,必须开发仪器和技术进步以用于广泛的应用中。为了发现最弱的核反应,必须确定任何释放的单个光子的总能量检测系统的最大概率。在这项工作中,提出了一种新的数学方法来计算非对称多面体锗探测器的绝对全能峰值效率。这种类型的检测器可以排列成阵列,形成“封装的锗晶体的复杂检测器”,其立体角达到总立体角覆盖率的82%,即,具有最高的效率和良好的光谱响应质量。此外,光子路径长度被包含在数学方法中,以确定其在测量过程中通过不同材料(例如探测器活性介质和源-探测器系统之间的任何其他材料)的衰减。在这项工作中计算出的效率与已发布的蒙特卡洛模拟的效率之间的比较显示出很好的一致性和很小的差异。但是,当前工作中讨论的方法对于克服在识别放射性同位素的能量范围及其在核废料中的数量所面临的巨大困难方面,对核保障很有用。

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