Monte Carlo simulation by GEANT 4 and GESPECOR of in situ gamma-ray spectrometry measurements

Monte Carlo calculations of the HPGe detector efficiency for radioactivity measurement of large volume environmental samples

“…In reality, the lack of standard sources with different geometries and matrices makes the experimental determination of the detector efficiency, an arduous task (Abbas et al, 2002;Mostajaboddavati et al, 2006;Chirosca et al, 2013).…”

“…To reach this purpose, an attempt was made to develop locally a reliable computational model useful for environmental applications (Guti errez-Villanueva et al, 2008;Dababneh et al, 2014). The Monte Carlo (MC) method is well appropriate to perform the calibration and to reproduce the detector response for a variety of matrices and for different geometries with sufficient accuracy (Bochud et al, 2006;R odenas et al, 2007;Sima and Arnold, 2009;Chirosca et al, 2013).…”

Investigating the potentialities of Monte Carlo simulation for assessing soil water content via proximal gamma-ray spectroscopy

“…In this perspective, Monte Carlo simulations can overcome the limits of analytical solutions, which generally address the description of the sole unscattered gamma-ray flux, by providing information on the entire gamma spectra (Allyson and Sanderson, 1998;Androulakaki et al, 2016;Vlastou et al, 2006). In a Monte Carlo simulation all parameters can be separately controlled and uncertainties coming from temporary variations in the experimental conditions can be excluded, which is particularly relevant in relation to calibration procedures and feasibility studies (Chirosca et al, 2013;De Groot et al, 2009;Van der Graaf et al, 2011). This peculiarity makes the methodology highly versatile in terms of input boundary conditions and extraordinarily effective in both investigating the effects of individual variables (e.g.…”

Uncertainty associated with Monte Carlo radiation transport in radionuclide metrology

“…Examples range from radiation protection of restricted areas to the understanding of energy deposition at the cellular level [1]. In radionuclide metrology, MC calculations have been proven as very useful for gamma spectrometer calibration [2][3][4][5][6][7], but also for gamma spectrometer self-attenuation [8,9] or coincidence summing [10,11], dose calibrators [12,13], extrapolation ionization chambers [14], assay of radioactive waste [15], primary measurement like 4 πγ counting [16] or triple to double coincidence ratio [17] methods. Several general purpose Monte Carlo codes, such as GEANT [18], EGS [19], MCNP [20], and PENELOPE [21], can be tailored to particular applications and also, special purpose codes are available to solve specific problems.…”