Fluorescence Nuclear Track Detectors (FNTDs) are part of a new technology developed for particle detection and applicable to personal neutron dosimetry. The objective of this study is to simulate the FNTD fast neutron response to: (i) assess and understand the performance of the existing neutron dosimeter design (Landauer Inc.) and its associated single layer track-spots analysis; and (ii) evaluate the potential information that can be obtained by the analysis of the 3D reconstructed recoil proton trajectories. To achieve that, a FLUKA Monte Carlo (MC) model of the current FNTD design was developed and the FNTD response was investigated for mono-energetic neutrons and the ²⁵²Cf and ²⁴¹AmBe neutron sources. The investigation of the recoil proton densities behind the different converters showed that the single layer analysis and dose calculation algorithm, based on the comparison and subtraction of the track densities behind the different converters, works properly only up to neutron energies ~13 MeV. Above this neutron energies, recoil protons generated in the detector housing (PE) have a range larger than the thickness of the PTFE and ⁶Li-enriched glass, reaching the FTND and, therefore, adding to the signal in these detection regions and influencing the secondary electron discrimination and the energy determination algorithm. MC simulations show that the FNTD 3D reconstructed recoil proton tracks can provide estimates of the irradiation angles and average neutron energy. The results show that the angle or displacement (dX/dZ or dY/dZ) distributions of the recoil proton tracks can be used to obtain information on irradiation angle; the angle with the detector's normal (polar angle), the most important because of its influences on the FTND sensitivity, can be determined in laboratory and for irradiation angles < 60° with an 4° uncertainty already for doses > 4.5 mSv in the case of a²¹⁴AmBe neutron irradiation. The neutron field mean energy can also be determined for normal irradiation by analysing the depth distribution of the recoil proton tracks already for a minimum of 150 tracks, or 2.5 mSv for ²⁴¹AmBe, assuming a scanned area is ~2.0 mm². Therefore, the present study contributes to understanding the performance of the current FNTD design and analysis for neutron dosimetry and investigates a new detector evaluation approach to gain additional information on the irradiation conditions.

荧光核径迹探测器 (FNTD) 是为粒子探测而开发的新技术的一部分，适用于个人中子剂量测定。本研究的目的是模拟 FNTD 快速中子响应以： (i) 评估和了解现有中子剂量计设计 (Landauer Inc.) 的性能及其相关的单层轨迹点分析；(ii) 评估通过分析 3D 重建反冲质子轨迹可以获得的潜在信息。为此，开发了当前 FNTD 设计的 FLUKA 蒙特卡罗 (MC) 模型，并研究了单能中子和²⁵² Cf 和²⁴¹AmBe 中子源。对不同转换器后面的反冲质子密度的调查表明，基于不同转换器后面轨道密度的比较和减法的单层分析和剂量计算算法，仅在中子能量高达 ~13 MeV 时正常工作。在此中子能量之上，探测器外壳 (PE) 中产生的反冲质子的范围大于 PTFE 的厚度和⁶富锂玻璃，到达 FTND，因此，添加到这些检测区域中的信号并影响二次电子鉴别和能量确定算法。MC 模拟表明，FNTD 3D 重建的反冲质子轨迹可以提供辐照角和平均中子能量的估计值。结果表明，反冲质子轨迹的角度或位移（dX/dZ或dY/dZ）分布可用于获得辐照角信息；与探测器法线的角度（极角），由于其对 FTND 灵敏度的影响而最重要，可以在实验室中确定，对于< 60° 的辐照角，在剂量 > 4.5 mSv 的情况下，已经有 4° 的不确定性一个²¹⁴AmBe 中子辐照。还可以通过分析反冲质子轨迹的深度分布来确定正常照射的中子场平均能量，其中至少有 150 个轨迹，或者²⁴¹ AmBe为 2.5 mSv ，假设扫描区域为 ~2.0 mm ²。因此，本研究有助于了解当前 FNTD 设计和中子剂量分析的性能，并研究一种新的探测器评估方法，以获得有关辐照条件的更多信息。