Abstract
The spectrum-dose conversion operators (hereafter, G(E) function) were calculated for CsI(Tl) scintillation counters based on the response functions obtained by a Monte Carlo simulation code, MCNP5, in the photon energy range from 40 to 10,000 keV. The G(E) functions were determined in the cases of crystal sizes 5.5 × 5.5 × 5.5, 10 × 10 × 10, 13 × 13 × 20 and 38 × 38 × 25 mm3 for ambient dose, H*(10). It was found that the values of H*(10) deduced from the pulse-height spectra and the G(E) function agreed with those of H*(10) evaluated in the calibration field in Japan Atomic Energy Agency (JAEA) within 2% in the case of irradiations by 137Cs, 226Ra and 60Co source, by the measurements using a scintillation counter whose crystal size was 13 × 13 × 20 mm3.
