Development and validation of a Monte Carlo simulation of a gamma camera using MCNP
This paper describes the development and validation of a Monte Carlo (MC) code to simulate the performance characteristics of a gamma camera with respect to energy and spatial distribution of detected photons, for nuclear medicine applications. There were 2 possibilities: either the MC code EGS4 could be used, giving all the information regarding particle physics with very limited tools for 3-dimensional (3D) geometry representation, or a Monte Carlo software package (MCNP) could be used, having good 3D geometric modelling features but not equipped with tools for interaction classification. It was decided to modify the MCNP by including an additional code to permit output of the history of each photon (scatter history, energy deposited in crystal and location). The code also tracks the production of detection of lead x-rays in the collimator. Energy and intrinsic resolution are simulated by Gaussian blurring functions. Variation in energy resolution versus energy was determined experimentally and included in the model. First results are given and evaluated with respect to experimental results.
Bibliographic Reference: Paper presented: The Society of Nuclear Medicine 45th Annual Meeting, Toronto (CA), 7-11 June 1998
Availability: Available from (1) as Paper EN 41375 ORA
Record Number: 199810703 / Last updated on: 1998-06-08
Original language: en
Available languages: en