Radiation Protection Dosimetry · 1990 · 11 citations · 0 references
EngineeringNuclear EngineeringNuclear PhysicsRadiation DetectionRadiation DosimetryAbsorbed DoseGamma-ray DetectionGamma-ray DetectorsGamma-ray InstrumentationNeutron DetectionRadiation Dose MeasurementAccident DosimetryDose-rate DependenceGamma DosimetryGlow CurvesNeutron DetectorsNeutron Equivalent DoseNeutron IrradiationNeutron Irradiation Effects
DTGN-2 (7LiF:Mg,Ti) gamma-neutron detectors are prepared as monocrystal discs 10 mm across and 3 mm thick. Selective determination of gamma and neutron doses in mixed gamma-neutron fields with these detectors is based on the use of two peaks on the glow curve whose efficiencies have different dependence on the LET. The method based on this effect has been developed to separate the gamma and neutron doses. Dose dependence obtained after neutron irradiation is linear in the range of 10-3 - 50 Gy and the minimum measurable dose is 5x10-4 Gy. Neutron sensitivities, expressed as gamma Gy per Gy, are 0.6, 0.8 and 1.1 with mean energies 1.9, 4.5 and 14 MeV, respectively. The parameters obtained permit possible application of the detector in accident dosimetry.