中子辐射场中CdZnTe辐射探测器的损伤产生机理及性能退化

IF 2.8 2区工程技术 Q3 MATERIALS SCIENCE, MULTIDISCIPLINARY

Journal of Nuclear Materials Pub Date : 2025-03-26 DOI:10.1016/j.jnucmat.2025.155781

Qinzeng Hu , Lingyan Xu , Zhixin Tan , Ming Hao , Lu Liang , Yingming Wang , Zhentao Qin , Lixiang Lian , Chongqi Liu , Yanyan Lei , Wei Zheng , Wanqi Jie

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引用次数: 0

摘要

在核电站等环境中使用的半导体辐射探测器不可避免地会暴露在中子、γ射线等高能辐射中，这些辐射会破坏半导体的晶体结构，从而降低探测器的性能。在这里，我们研究了中子辐照对CdZnTe探测器微观结构、光电和辐射探测性能的影响。低温光致发光（PL）光谱表明，随辐照通量的增加，晶体中位错相关缺陷的浓度增加。与未辐照晶体相比，辐照晶体的红外透过率降低，这也表明位错密度增加。透射电镜（TEM）分析了辐照后CdZnTe晶体中存在层错、层错偶极子和位错锁。在5.6 × 1010 n/cm2辐照下，241Am@100 V的γ射线能量分辨率由辐照前的5.86%下降到10.72%。此外，CdZnTe探测器的电子迁移寿命积（μτ）e从辐照前的4.8 × 10-3 cm2/V降低到5.6 × 1010 n/cm2辐照后的7.02 × 10-4 cm2/V。I-V测试表明，CdZnTe探测器的势垒高度随着中子辐照通量的增加而降低，导致其电阻率降低。飞行时间（TOF）测试表明，辐照后电子迁移率随辐照通量的增加而降低。值得注意的是，本研究中使用的最大中子通量为3.9 × 1011 n/cm2，在该通量下CdZnTe辐射探测器并未完全损坏。本研究主要研究中子辐照下CdZnTe晶体的辐射损伤机理、诱导缺陷特征和性能退化，旨在为提高探测器的抗辐射性能提供理论指导。

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Damage generation mechanism and performance degradation of CdZnTe radiation detectors in neutron radiation field

Semiconductor radiation detectors used in nuclear power plants and other environments are inevitably exposed to neutron, γ-ray and other high-energy radiation, which can damage the crystal structure of semiconductors and thus degrade the detector performance. Here, we investigate the effects of neutron irradiation on the microstructure, photoelectric and radiation detection performance of CdZnTe detectors. Low-temperature photoluminescence (PL) spectra show that the dislocation related defect concentration in the irradiated crystals increases with increasing fluence. The infrared (IR) transmittance of the irradiated crystal decreases compared with that of the unirradiated crystal, which also indicates an increase in the dislocation density. The presence of stacking faults, stacking fault dipoles and dislocation locks in the irradiated CdZnTe crystals has been revealed by transmission electron microscopy (TEM). The energy resolution of γ-ray from ²⁴¹Am@100 V is degraded from 5.86 % before irradiation to 10.72 % after irradiation at 5.6 × 10¹⁰ n/cm². In addition, the mobility-lifetime product of electron (μτ)_e in CdZnTe detectors is reduced from 4.8 × 10^-3 cm²/V before irradiation to 7.02 × 10^-4 cm²/V after irradiation at 5.6 × 10¹⁰ n/cm². I-V test show that the barrier height of the CdZnTe detector decreases with the increase of neutron irradiation fluence, leading to a decrease in resistivity. Time-of-flight (TOF) tests demonstrate that the electron mobility after irradiation decreases with increasing irradiation fluence. Notably, the maximum neutron fluence used in this study is 3.9 × 10¹¹ n/cm², at which the CdZnTe radiation detector is not completely damaged. This study mainly investigates the radiation damage mechanism, induced defect characteristics and performance degradation of CdZnTe crystals by neutron irradiation, aiming to provide theoretical guidance for improving the radiation-resistant properties of detectors.

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来源期刊

Journal of Nuclear Materials 工程技术-材料科学：综合

CiteScore

5.70

自引率

25.80%

发文量

601

审稿时长

63 days

期刊介绍： The Journal of Nuclear Materials publishes high quality papers in materials research for nuclear applications, primarily fission reactors, fusion reactors, and similar environments including radiation areas of charged particle accelerators. Both original research and critical review papers covering experimental, theoretical, and computational aspects of either fundamental or applied nature are welcome. The breadth of the field is such that a wide range of processes and properties in the field of materials science and engineering is of interest to the readership, spanning atom-scale processes, microstructures, thermodynamics, mechanical properties, physical properties, and corrosion, for example. Topics covered by JNM Fission reactor materials, including fuels, cladding, core structures, pressure vessels, coolant interactions with materials, moderator and control components, fission product behavior. Materials aspects of the entire fuel cycle. Materials aspects of the actinides and their compounds. Performance of nuclear waste materials; materials aspects of the immobilization of wastes. Fusion reactor materials, including first walls, blankets, insulators and magnets. Neutron and charged particle radiation effects in materials, including defects, transmutations, microstructures, phase changes and macroscopic properties. Interaction of plasmas, ion beams, electron beams and electromagnetic radiation with materials relevant to nuclear systems.