Liang Xuwen, Zhao Dong, Jia Wenbao, Hei Daqian, Cheng Can
Department of Nuclear Science and Technology, Nanjing University of Aeronautics and Astronautics, Nanjing, 211106, China.
Department of Nuclear Science and Technology, Nanjing University of Aeronautics and Astronautics, Nanjing, 211106, China; Collaborative Innovation Center of Radiation Medicine of Jiangsu Higher Education Institutions, Suzhou, 215000, China.
Appl Radiat Isot. 2023 Jun;196:110778. doi: 10.1016/j.apradiso.2023.110778. Epub 2023 Mar 15.
Owing to the developments in prompt gamma neutron activation analysis (PGNAA) and prompt gamma ray activation imaging (PGAI), it is necessary to develop an online thermal neutron distribution measurement method. The CdZnTe detector is considered as an alternative thermal neutron detector because of its high thermal neutron capture cross section. In this study, the thermal neutron field of an Am-Be neutron source was determined by CdZnTe detector. The intrinsic neutron detection efficiency of CdZnTe detector was calculated by using indium foil activation, and the value was 3.65%. Then the characteristics of neutron source were conducted with the calibrated CdZnTe detector. The thermal neutron fluxes in front of beam port were measured at several distances ranging from 0 cm up to 28 cm. Thermal neutron field at distances of 1 cm and 5 cm were also measured. The experimental data were then compared with Monte Carlo simulation. The results demonstrated that the simulated data agree well with experimental measurements.
由于瞬发伽马中子活化分析（PGNAA）和瞬发伽马射线活化成像（PGAI）的发展，有必要开发一种在线热中子分布测量方法。碲锌镉探测器因其高热中子俘获截面而被视为一种替代热中子探测器。在本研究中，用碲锌镉探测器测定了镅铍中子源的热中子场。利用铟箔活化计算了碲锌镉探测器的本征中子探测效率，其值为3.65%。然后用校准后的碲锌镉探测器对中子源的特性进行了研究。在从0厘米到28厘米的几个距离处测量了束流口前方的热中子通量。还测量了1厘米和5厘米距离处的热中子场。然后将实验数据与蒙特卡罗模拟进行比较。结果表明，模拟数据与实验测量结果吻合良好。
