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arXiv 2107.01047physics.ins-detnucl-ex
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基于乏燃料表征用EJ-426 Scintillator屏的中子探测器现场性能评价

Evaluation of the in-situ Performance of Neutron Detectors based on EJ-426 Scintillator Screens for Spent Fuel Characterization

Hanno Perrey, Linus Ros, Mikael Elfman, Ulrika Bäckström, Per Kristiansson, Anders Sjöland

摘要:

在恶劣的伽马射线环境中可靠地探测中子是建立非破坏性乏核燃料定性方法的一个重要方面。在这项研究中,我们提出的结果,从扩展原位监测的探测器系统组成的市售组件:EJ-426,一个$^6$富锂固态闪烁体材料敏感的热中子,和两种不同类型的滨松光电倍增管(PMT)。在8个月的时间里,这些探测器在瑞典奥斯卡港临时储存设施CLAB储存的乏核燃料附近运行。在测量位置处,探测器连续暴露于估计的约为1000 μ m的中子通量。280 n/s $\cdot$ cm $^2$,伽马射线剂量率约为6 Sv/h。使用离线软件算法,在数据中识别出中子脉冲。在高达35千克的整个研究剂量范围内,探测器系统都在发挥作用,并发出可探测的中子信号。它们的性能由已识别中子的数量来衡量,下降到初始值的30%左右。辐照组件的调查表明,这种退化是由于所涉及的材料的光学透明度降低,以及由于连续的高电流的PMT增益的减少。通过所施加的高电压的升压来增加PMT的增益允许部分地补偿检测灵敏度的这种损失。在测量期间的积分中子注量被实验验证为在$5 \cdot 10^9$ n/cm $^2$的数量级。利用MCNP 6.2对装置和中子通量进行了模拟计算。

英文摘要:

The reliable detection of neutrons in a harsh gamma-ray environment is an important aspect of establishing non-destructive methods for the characterization of spent nuclear fuel. In this study, we present results from extended in-situ monitoring of detector systems consisting of commercially available components: EJ-426, a $^6$Li-enriched solid-state scintillator material sensitive to thermal neutrons, and two different types of Hamamatsu photomultiplier tubes (PMT). Over the period of eight months, these detectors were operated in close vicinity to spent nuclear fuel stored at the interim storage facility CLAB, Oskarshamn, Sweden. At the measurement position the detectors were continuously exposed to an estimated neutron flux of approx. 280 n/s $\cdot$ cm$^2$ and a gamma-ray dose rate of approx. 6 Sv/h. Using offline software algorithms, neutron pulses were identified in the data. Over the entire investigated dose range of up to 35 kGr, the detector systems were functioning and were delivering detectable neutron signals. Their performance as measured by the number of identified neutrons degrades down to about 30% of the initial value. Investigations of the irradiated components suggest that this degradation is a result of reduced optical transparency of the involved materials as well as a reduction of PMT gain due to the continuous high currents. Increasing the gain of the PMT through step-ups of the applied high voltage allowed to partially compensate for this loss in detection sensitivity. The integrated neutron fluence during the measurement was experimentally verified to be in the order of $5 \cdot 10^9$ n/cm$^2$. The results were interpreted with the help of MCNP6.2 simulations of the setup and the neutron flux.

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