Plastic scintillator detector for qualitative and quantitative measurements of gamma radiation  

作　　者：Vaishali M.Thakur Nitin Bhosale Amit Jain Mukesh Sharma L.M.Chaudhari Probal Chaudhury 

机构地区：[1]Radiation Safety Systems Division,Bhabha Atomic Research Centre,Trombay,Mumbai,400085,India [2]Department of Physics,Nowrosjee Wadia College,Pune,411001,India

出　　处：《Radiation Detection Technology and Methods》2023年第4期578-588,共11页辐射探测技术与方法（英文）

摘　　要：Background Plastic scintillator detectors are rugged and easily manufactured in desired shape,sizes and response time to gamma radiation is prompt as compared with any other scintillator detectors.Being popular these detectors are used in radiation monitors one of the application to restrict radioactive material movement.These are used in gross counting mode to know the presence of radioactivity.Therefore secondary survey is required to know the nature of the radionuclides.Purpose The feasibility study of Cylindrical Plastic Scintillator Detector(CPSD)was carried out for the qualitative and quantitative assessment of gamma emitting radionuclides.Methods In this work limited gamma spectrometry was carried out using NE110 equivalent cylindrical plastic scintillating material of 5.1 cm diameter and 100 cm long.CPSD is optically coupled to photomultiplier tube(PMT).The detector signal is processed using preamplifier,shaping amplifier and further analysed by a multi channel analyser(MCA).CPSD gamma spectrum consists of Compton continuum and Gaussian shaped Compton edge energy(λ_(e))appearing as Compton maxima energy(λ_(max)).Photon transport simulation is used to characterizeλ_(max) as a signature for radionuclides emitting gamma energy/energies.In case of unresolved gamma energies,it appears as weighted effective Compton maxima energy.The prominent gamma energies observed across nuclear industries are in the energy range 0.03–3 MeV.It is grouped as low energy,intermediate energy,high energy and ultra-high energy window.The simulated spectrum is obtained suing Gaussian broadening parameters deduced from experimentally measured spectrum.The efficiency response function is developed from simulated response of detector to standard gamma sources under known source detector configurations.Results The mono energetic gamma emitting radioisotopes are identified againstλ_(max) from data library.Qualitative analysis of spectrum is used to discriminate artificial radioactive material from naturally occurring radioactive ma

关 键 词：Plastic scintillator detector Gaussian broadening Compton edge Compton maxima Weighted effective Compton maxima Gamma spectrum Multi-channel analyzer 

分 类 号：O57[理学—粒子物理与原子核物理]