A conceptual design and performance studies for a collimated neutron flux monitor and neutron spectrometer for the Divertor Tokamak Test (DTT) facility are presented. This study is based on the single-null divertor configuration and for “Half Power” and “Full power” scenarios with 15 MW of negative-ion NBI, 29 MW of ECH and 3 MW of ICRF heating with a maximum neutron yield of $1.5\times {10}^{17}$ s${}^{-1}$. Fast ion distributions (both from auxiliary heating systems and fusion born) have been simulated in TRANSP/NUBEAM and the corresponding neutron energy spectra have been calculated using DRESS. Synthetic diagnostics have been implemented to determine the neutron fluxes and spectra at the detector location. Neutron emissivity profiles, plasma position, core ion temperature and the ratio of thermal and non-thermal D ion populations can be obtained with good accuracy and time resolution.

介绍了分流器托卡马克试验（DTT）设施的准直中子通量监测仪和中子能谱仪的概念设计和性能研究。本研究基于单零偏滤器配置，适用于“半功率”和“全功率”方案，其中负离子NBI为15 MW，ECH为29 MW，ICRF为3 MW，最大中子收率为9 MW。$1.5\times {10}^{17}$ s${}^{-\mathrm{1个}}$。在TRANSP / NUBEAM中已经模拟了快速离子分布（来自辅助加热系统和聚变），并且已经使用DRESS计算了相应的中子能谱。已经进行了综合诊断以确定在探测器位置的中子通量和光谱。可以以良好的精度和时间分辨率获得中子发射率曲线，等离子体位置，核心离子温度以及热和非热D离子种群的比率。