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Using Monte Carlo Methods to Estimate Efficiencies of Gamma-Ray Emitters With Complex Geometries



Svetlana Nour, Matthew Mille, Kenneth G. Inn


In the event of a radioactive disaster, one of the biggest tasks is to estimate the radiation dosage received by people to determine the actions of emergency response teams. The first and the most rapid screening method of internally contaminated people in case of an emergency response is to perform in-vivo measurements for gamma emitters. Development of virtual gamma- ray calibration techniques will be critical for emergency in-vivo measurements because there are inadequate numbers of phantom types to approximate all body shapes and sizes. The purpose of this project was to find a reliable way to estimate the efficiency of gamma systems using the Monte Carlo computation, and to validate that efficiency by making measurements of a standard geometry.Two geometries, a 5 mL ampoule and a Bottle Manikin Absorption (BOMAB) phantom head, spiked with Ga-67 were used as standard geometries. The radioactive objects are measured at a number of distances from High Purity Germanium (HPGe) detector, and the experimental efficiency for our gamma spectrometry system is determined. The same set of experiments is then modeled using the Monte Carlo N-Particle Transport Code (MCNP). The conclusion of this project is that computational derivation detector efficiency calibration can be comparable to those derived from physical standards.
Journal of Radioanalytical Chemistry


mathematical modeling, MCNP, Monte Carlo, simulation


Nour, S. , Mille, M. and Inn, K. (2007), Using Monte Carlo Methods to Estimate Efficiencies of Gamma-Ray Emitters With Complex Geometries, Journal of Radioanalytical Chemistry, [online], (Accessed May 26, 2024)


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Created March 2, 2007, Updated February 17, 2017