National Centre for Nuclear Research, Nuclear Facilities Operations Department, Radiological Metrology and Biomedical Physics Division, 7 Andrzeja Sołtana Street, 05-400 Otwock, Poland.
Faculty of Mechatronics, Institute of Metrology and Biomedical Engineering, Warsaw University of Technology, 8 św. Andrzeja Boboli Street, 02-525 Warsaw, Poland.
Radiat Prot Dosimetry. 2023 Oct 11;199(15-16):1862-1866. doi: 10.1093/rpd/ncad169.
In the study, the passive multi-layer neutron spectrometer, based on thermoluminescence detectors, was tested in a calibration laboratory with 239Pu-Be and 252Cf isotopic sources. MCNP code was used for the calculation of the response functions for the neutron energy range from 1 meV to 100 MeV. It was also utilised for initial guess spectra calculations. Deconvolution was performed with MAXED and GRAVEL deconvolution codes resulting in the neutron spectra defined at the measuring point in the calibration laboratory.
在这项研究中，基于热释光探测器的无源多层中子谱仪在一个校准实验室中使用 239Pu-Be 和 252Cf 同位素源进行了测试。MCNP 代码用于计算中子能量范围为 1 毫电子伏特至 100 兆电子伏特的响应函数。它还用于初始猜测谱计算。使用 MAXED 和 GRAVEL 反卷积代码进行反卷积，得出在校准实验室中的测量点定义的中子谱。
