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Design and development of a plastic scintillator based whole body β/γ contamination monitoring system

Nuclear Science and Techniques 2021年第5期32卷 33-42页

作者： Vaishali M.Thakur Amit Jain P.Ashokkumar Rekha Anilkumar Pravin Sawant probal chaudhury L.M.Chaudhari Radiation Safety Systems Division Bhabha Atomic Research CentreMumbai 400085India Health Physics Division Bhabha Atomic Research CentreMumbai 400085India Department of Physics Nowrosjee Wadia CollegePuneMaharashtra 411001India

Plastic scintillation detectors based whole body β/γ contamination monitors are developed for use in radiation *** microcontroller-based multi-detector system uses 13 plastic scintillator detectors,with minimized dead detection zones,monitoring the whole body,and conforming to the contamination limit prescribed by the regulatory *** system has the features for monitoring hands,feet,head,and faceβ/γusing contamination monitors and portal exit *** can detect gamma sources at a dose rate of 10 n Gyh^(-1).The system is calibrated using b sources^(90)Sr/^(90)Y,^(204)Tl,and^(36)Cl,and the efficiency is found to be 29%,22%,and 18%,***β/γcontaminationis0.15 Bqcm^(-2),which is significantly less than the minimum detection objectives on head,face,hands,and feet.

关键词： Plastic scintillation detector Contamination monitor Microcontroller Minimum Detection Objective(MDO) Minimum Detection Concentration(MDC)

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Plastic scintillator detector for qualitative and quantitative measurements of gamma radiation

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Radiation Detection Technology and Methods 2023年第4期7卷 578-588页

作者： Vaishali M.Thakur Nitin Bhosale Amit Jain Mukesh Sharma L.M.Chaudhari probal chaudhury Radiation Safety Systems Division Bhabha Atomic Research CentreTrombayMumbai400085India Department of Physics Nowrosjee Wadia CollegePune411001India

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 *** popular these detectors are used in radiation monitors one of the application to restrict radioactive material *** are used in gross counting mode to know the presence of *** secondary survey is required to know the nature of the *** The feasibility study of Cylindrical Plastic Scintillator Detector(CPSD)was carried out for the qualitative and quantitative assessment of gamma emitting *** In this work limited gamma spectrometry was carried out using NE110 equivalent cylindrical plastic scintillating material of 5.1 cm diameter and 100 cm *** 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/*** case of unresolved gamma energies,it appears as weighted effective Compton maxima *** prominent gamma energies observed across nuclear industries are in the energy range 0.03–3 *** is grouped as low energy,intermediate energy,high energy and ultra-high energy *** simulated spectrum is obtained suing Gaussian broadening parameters deduced from experimentally measured *** efficiency response function is developed from simulated response of detector to standard gamma sources under known source detector *** The mono energetic gamma emitting radioisotopes are identified againstλ_(max) from data *** analysis of spectrum is used to discriminate artificial radioactive materi

关键词： Plastic scintillator detector Gaussian broadening Compton edge Compton maxima Weighted effective Compton maxima Gamma spectrum Multi-channel analyzer

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