Abstract

This paper focuses on the feasibility of fast neutron energy spectrum measurement. The MCNPX and Geant4 are used to simulate two conversion models of stacking neutrons to protons in the triple GEM cathode coupled with multilayer polyethylene, with five kinds of single-energy neutron sources and Am-Be continuous neutron sources taken as research objects. The response function to 160 single energy neutrons and the recoil proton spectrum distribution of the above sources of the detection system are obtained by simulation. Using GRAVEL algorithm and MLEM algorithm and through simulation, the recoil proton spectra of six kinds of fast neutron sources are obtained, and they are further analyzed. The spectrum outcome is compared with the standard input spectrum, showing that they are in good agreement with each other. The relative uncertainty of the unfolding spectrum is around 10%–15%. In this part the relation of gas detector with the precision of unfolding spectrum is also discussed. The result shows that when the energy resolution of micro-pattern gas detection is better than 30%, the accuracy of fast neutron spectrum can meet the needs of practical applications. Furthermore, a new transformation model is proposed based on previous experiments and proves the feasibility of applying micro-pattern gas detector to fast neutron detection of simulation. Moreover, spectrum reconstruction can be achieved by using the obtained recoil proton spectrum combined with a suitable inversion algorithm. The modeling and spectrum analysis of this study can provide a different method of applying the fast neutron detection system composed of micro-pattern gas detectors to the detection of unknown fast neutron sources and also to the source recognition through spectrum reconstruction.

Highlights

  • Simulation results of Geant4 and MCNPX for the optimal thickness and detection efficiency of different neutron sources interacting with polyethylene

  • Response functions corresponding to different neutron energies

  • Error levels of the two MCNPX structures and Geant4 simulation results after unfolding by the MLEM and GRAVEL algorithms

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Summary

Introduction

利用 MCNPX 和 Geant4 分别模拟了基于 Triple GEM 设计的中子探测器对不同中子源的响 应, 获得了由 160 个单能中子响应函数组成的探测 器响应矩阵, 以及探测器对 Am-Be 中子源的反冲 质子能谱. Schematic diagram of the Triple GEM-based neutron detector (The blue color is HDPE, and the green part is the mixture of CO2 and Ar). The function of the detector efficiency with different polyethylene thicknesses. Geant4 和 MCNPX 对三种不同中子 源与聚乙烯相互作用的最佳厚度和探测效率的模 拟结果对比如表 1 所列. 由于 Geant4 和 MCNPX 两者物理过程中使 用的截面库和中子通量的计算方式不同, 因此探测

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