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The safety measures for nuclear reactors are constantly advancing in line with the progress in utilizing nuclear reactors as power sources. Furthermore, the capabilities of early detection systems in nuclear reactors are always evolving to provide the most efficient detectors. The rise of gamma radiation levels serves as an indicator in the safety system of nuclear reactors, and it refers to the gamma radiation detector. An outcome of the advancement of gamma radiation detectors is the creation of detectors that possess exceptional capabilities but come with an expensive cost. Poly Vinyl Toluene (PVT) plastic can function as a gamma detector and is cost-effective. This study aims to investigate the possibility of utilizing PVT-based scintillation detectors as a cost-effective solution for incorporating early detection capabilities into nuclear reactor safety systems. The work involved the characterization of PVT-based scintillation detectors, followed by a comparison with commercially available detectors. This research is concerned with the efficiency of the detector.
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1 Joint Doctoral Program for Sustainability Research, The University of Electro-communications , Tokyo, Japan; Department of Physics, Faculty of Mathematics and Natural Sciences, Bandung Institute of Technology Ganesha No. 10 Bandung, Indonesia
2 Department of Physics, Faculty of Mathematics and Natural Sciences, Bandung Institute of Technology Ganesha No. 10 Bandung, Indonesia; Department of Nuclear Science and Engineering, Faculty of Mathematics and Natural Sciences, Bandung Institute of Technology Ganesha No. 10 Bandung , Indonesia
3 Department of Nuclear Science and Engineering, Faculty of Mathematics and Natural Sciences, Bandung Institute of Technology Ganesha No. 10 Bandung , Indonesia; Nuclear Energy Research Organization, National Research and Innovation Agency (BRIN) , Indonesia
4 Department of Nuclear Science and Engineering, Faculty of Mathematics and Natural Sciences, Bandung Institute of Technology Ganesha No. 10 Bandung , Indonesia