Saveh_Soil_Radioactivity_Data_Baseline
Description
Gamma spectrometry raw data and radiological hazard parameters for soil samples collected from Saveh, Iran This dataset contains the raw gamma spectrometry results and derived radiological parameters for surface soil samples collected from seven locations in Saveh, Iran. The activity concentrations of naturally occurring radionuclides including Ra-226, Th-232 and K-40 were measured using a high-purity germanium (HPGe) detector with 40% relative efficiency and a counting time of 86400 seconds. The dataset includes: • Raw activity concentrations (Bq/kg) and their combined uncertainties • Geographic coordinates of sampling locations • Representative gamma peak information (energy, emission probability and net counts) • Absorbed dose rate in air (nGy/h) • Annual effective dose (mSv/y) Activity concentrations were calculated using standard gamma spectrometry equations based on net peak area, detector efficiency, gamma emission probability and counting time. Combined uncertainties include counting statistics, efficiency calibration uncertainty, gamma emission probability and peak fitting uncertainty. This dataset supports the results and conclusions presented in the associated research article and enables reproducibility of the radiological assessment.
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Steps to reproduce
Soil samples were collected from multiple locations in Saveh city, Markazi Province, Iran. At each sampling point, approximately 1 kg of surface soil (depth 0–30 cm) was collected, homogenized, dried at 105 °C to constant weight, and sieved through a 2 mm mesh. The prepared samples were sealed in Marinelli beakers and stored for at least 30 days to allow secular equilibrium between ²²⁶Ra and its progeny. Gamma spectrometric analysis was performed using a high-purity germanium (HPGe) detector with appropriate energy and efficiency calibration. Each sample was measured for 24 hours to obtain statistically reliable spectra. Activity concentrations of ²²⁶Ra, ²³²Th, and ⁴⁰K were determined from their characteristic gamma emission peaks. The analysis of spectra was performed using standard gamma spectroscopy software. Radiological parameters, including activity concentrations with combined uncertainties, absorbed dose rate (D), and annual effective dose, were calculated using internationally accepted equations. All calculations were performed using Microsoft Excel.
Institutions
- Islamic Azad University of ParandTehran, Robāţ Karīm