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This paper presents the performance of polystrene based plastic scintillator produced in Turkish Energy, Nuclear and Mineral Research Agency (TENMAK). The scintillator is manufactured using thermal polymerization of commercially available styrene monomer doped with first and second fluorescent dyes. The absorption spectrum of the scintillator exhibited two absorption bands at 225 nm and 340 nm, with an absorption edge observed at 410 nm. The wavelength of the emitted light was measured in the range of 400–800 nm, with a maximum intensity at 427 nm. Internal conversion electrons from the 137Cs source were used to evaluate the characteristics of the new scintillator, particularly its light yield. As the light readout the MAPD-3NM type silicon photomultiplier array (4 × 4) with an active area of 15 × 15 mm 2 , assembled using single MAPDs with an active area of 3.7 × 3.7 mm 2 , was used. The light yield of the scintillator was determined to be 6134 photons/MeV. In addition, the efficiency of the scintillator for gamma rays with an energy of 662 keV was found out to be approximately 1.8%. CmBe neutron source was employed to evaluate its fast neutron detection performance. However, neutron/gamma discrimination using pulse shape discrimination (charge integration) method was not observed. The results demonstrate the potential of produced plastic scintillator for various applications, particularly in radiation monitoring and detection systems. • The scintillator is manufactured using thermal polymerization of commercially available styrene monomer doped with first and second fluorescent dyes. • Plastic scintillator exhibits two absorption bands at 225 and 340 nm, with an absorption edge observed at 410 nm. • The efficiency of the scintillator for gamma rays with an energy of 662 keV was found out to be approximately 1.8%. • The plastic scintillator coupled to micropixel avalanche photodiode demonstrated effective detection of beta particles emitted by 137Cs and 90Sr sources, with an energy resolution of 25% for monoenergetic (626 keV) electrons. [ABSTRACT FROM AUTHOR]

The dose and linear energy transfer (LET) dependence of the radiophotoluminescence (RPL) response was evaluated for RPL glass detectors, taken from the environmental dosimeter type SC-1, using a clinical 100 MeV and 200 MeV scanning pencil proton beam. The measurements were performed at different positions along the Bragg curves. The fluence-averaged (LET f) and dose-averaged (LET d) LET at the positions of the detectors were calculated using two Monte Carlo codes (MCNP and PHITS). Before measurements in proton beams, the linearity of the dose response for the dose range of interest (up to 10 Gy) was checked and confirmed in a Co-60 gamma ray field, since the FGD-202 reader for SC-1 dosimeters is usually used for doses up to 1 Gy and we found no data for higher doses in the literature. For proton beams, the linear dose response was determined for the doses investigated from 0.5 Gy to 8.8 Gy. For the LET range, which corresponds to the LET d from 0.47 keV/μm to 4.70 keV/μm, a decrease in response with an increase in LET was observed. • The dose and LET dependence of response was evaluated for RPL glass detectors. • Clinical proton beams and environmental RPL dosimetry system were used. • Linear dose response in Co-60 gammas and 100 MeV proton beam was shown. • A decrease in response with increase in LET was observed. [ABSTRACT FROM AUTHOR]