Experimental and Simulation of Gamma Radiation Dose Rate for High Exposure Building Material

TL;DR

This study measures and simulates gamma radiation dose rates from high exposure building materials in Iran, comparing experimental data with Monte Carlo simulations to validate the modeling approach.

Contribution

It provides a validated simulation method for estimating gamma dose rates in various dwelling environments based on measured radioactivity.

Findings

Experimental and simulated dose rates closely agree.

Radioactivity levels in materials vary widely, affecting dose rates.

Simulation can be extended to different building types.

Abstract

Natural radioactivity concentrations in high exposure building materials are commonly used in Iran, which is measured a direct exposure by using {\gamma}-ray spectrometry. The values for 226Ra, 232Th and 40K were in the ranges 3.8 - 94.2, 6.5 - 172.2 and 556.9 - 1539.2 Bqkg-1, respectively. The absorbed dose rates in the standard dwelling room due to 238U, 232Th series and 40K were calculated with MCNPX code. The simulation and experimental results were between 7.95 - 41.74 and 8.36 - 39.99 nGy h-1, respectively. These results were compared with experimental outing and there was overlap closely. The simulation results are able to develop for any kind of dwelling places.