Abstract
In this study, we developed a remote gamma-ray spectroscopy system based on a fiber-optic radiation sensor (FORS) that is composed of an inorganic scintillator coated with reduced graphene oxide (RGO) and a plastic optical fiber (POF). As a preliminary experiment, we measured the transmitted light intensities using RGO membranes of different thicknesses with different wavelengths of emitted light. To evaluate the FORS performance, we determined the optimal thickness of the RGO membrane and measured the amounts of scintillating light and gamma energy spectra using radioactive isotopes such as 60Co and 137Cs. The amounts of scintillating light from the RGO-coated inorganic scintillators increased, and the energy resolutions of the gamma-ray spectra were enhanced. In addition, the gamma-ray energy spectra were measured using different types of RGO-coated inorganic scintillators depending on the lengths of the POFs for remote gamma-ray spectroscopy. It was expected that inorganic scintillators coated with RGO in FORS can deliver improved performance, such as increments of scintillating light and energy resolution in gamma-ray spectroscopy, and they can be used to identify nuclides remotely in various nuclear facilities.
Highlights
Published: 30 November 2021One of the most widely used gamma-ray detection methods is gamma-ray spectroscopy, which can be employed to determine the types and quantities of gamma-rayemitting radioisotopes in nuclear facilities such as nuclear power plants and radioactive waste-disposal sites [1,2]
Gamma-ray spectroscopy can be performed in the laboratory with radioisotope samples using a scintillating radiation detector that consists of an inorganic scintillator, a photomultiplier tube (PMT), a preamplifier, and a digitizer
RGOmembranes membranes inorganic scintillators according tonumthe ber of coatings. (a) Uncoated, (b) coated 1 time, (c) coated 3 times, (d) coated 10 times, and (e) coated number of coatings. (a) Uncoated, (b) coated 1 time, (c) coated 3 times, (d) coated 10 times, and
Summary
Published: 30 November 2021One of the most widely used gamma-ray detection methods is gamma-ray spectroscopy, which can be employed to determine the types and quantities of gamma-rayemitting radioisotopes in nuclear facilities such as nuclear power plants and radioactive waste-disposal sites [1,2]. Gamma-ray spectroscopy can be performed in the laboratory with radioisotope samples using a scintillating radiation detector that consists of an inorganic scintillator, a photomultiplier tube (PMT), a preamplifier, and a digitizer. The identification and quantification of gamma-emitting radioisotopes using in situ gamma-ray spectroscopy are critical in the decommissioning of nuclear facilities and the disposal of radioactive waste. In these cases, remote gamma-ray measuring systems are important for the safety of personnel. Remote gamma-ray measuring systems are important for the safety of personnel These systems should have good performance, such as high counting efficiency and good energy resolution, for use in gamma-ray spectroscopy [3,4].
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