No abstract

Localization of the scintillation detectors manufacturing process has many benefits because of the high detection efficiency of the detectors, user-friendly, and consistent with general research objectives. Using a photodiode instead of a photomultiplier tube (PMT) allows saving energy, shortening the detector volume, and removing high voltage power supply and amplifier. The combination of CsI(Tl) scintillator, avalanche photodiode, charge sensitive preamplifier, wide range amplifier, and power supply system has been integrated into the detector. This study presents new results in manufacturing a home-made scintillation detector using avalanche photodiode. The detectors of this type can be used in hospitals, in the nuclear laboratory of universities for the students training, etc.

The interference of gamma in neutron spectra reduces the accuracy of measurement results, especially when using the scintillation detector. The digital method can be used to identify either neutron or gamma pulses. In order to select the algorithm for NE213 scintillation detector, the Matlab Simulink tool was used to simulate neutron counting system. The results show that the figure of merits (FOM) of:rise-time discrimination method (RTD), pulsed gradient analysis (PGA) method, charge comparison method (CCM), and correlation pattern method (CPM) are 1.09, 0.66, 2.21 and 1.97, respectively.