The possibility of employing α-Al2O3:C (TLD-500) for estimation of gamma dose in mixed n-γ radiation fields by two peak method has investigated. It was found that the main peak can be reliably deconvoluted to two component glow peaks. The ratio of peak 2 to peak 1 in pure gamma ray radiation field (137Cs) is 1.49 whereas irradiation by Am-Be neutrons results in a ratio of 1.12. The precision of...

Neutron response Induced in Thermoluminescence Dosimeter TLD-700 chips due to reactions of thermal neutrons with slab phantom and Badge Dosimeter TLD-600,700 materials in a neutron-gamma mixed field was measured. Using the linear relationship between thermal neutron fluence and the thermal neutrons induced TL response with slab phantom, Badge-TLD Materials, an empirical relationship was introdu...

In this research work public dose of Kashan inhabitants has been evaluated. Average annual effective dose due to inhalation of radon gas as well as external exposure to gamma rays have been evaluated to be 2.77±0.22 mSv and 0.97±0.05 mSv respectively. This leads to average annual public dose of 3.74 ± 0.22 mSv. Passive methods such as TLD pellets of LiF:Mg,Cu,P and polycarb...

MgSO4:Cu phosphor was synthesized by solid state method. Optimum concentration of copper was determined at 0.1 mol%. Thermoluminescence characteristics of MgSO4:Cu was studied following gamma irradiation. A linear dose response was observed in dose range of 1Gy to 500Gy. Reusability of this sample was tested after 10 cycles of gamma irradiation and it revealed that the intensity remains approxi...

In this study, a mixture of waste lead mine Nakhlak and cement with different percentages of boric acid are used to construct a proper shield for gamma and neutron radiations emitted from the Am-Be source. Neutron dose rate reduction ​​by the prepared samples was investigated by thermal neutron irradiation system of Isfahan University, TLD 600 and TLD 700. Neutron dose rate changes, compressive...