Abstract

This work presents experimental dosimetry results for a new P103d brachytherapy seed, in accordance with the AAPM TG‐43U1 recommendation that all new low‐energy interstitial brachytherapy seeds should undergo one Monte Carlo (MC) and at least one experimental dosimetry characterization. Measurements were performed using TLD‐GR200A circular chip dosimeters using standard methods employing thermoluminescent dosimeters in a Perspex phantom. The Monte Carlo N‐particle (MCNP) code, version 5 was used to evaluate the dose‐rate distributions around this model P103d source in water and Perspex phantoms. The consensus value for dose‐rate constant of the IR06‐P103d source was found equal to 0.690 cG⋅h−1⋅U−1. The anisotropy function, F(r, θ), and the radial dose function, gL(r), of the seed were measured in Perspex phantom and calculated in both Perspex and liquid water phantom. The measured values were also found in good agreement with corresponding MC calculations.PACS number: 87.53.Jw

Highlights

  • The isotopes 125I and 103Pd are frequently used in low-dose rate (LDR) brachytherapy sources

  • Brachytherapy dose distributions were simulated with the version 5 of the Monte Carlo (MC) Radiation Transport Code written by Los Alamos National Laboratory.[13]. The MCPLIB04 photon cross-sectional library was applied using data from ENDF/B-VI.[14]. The results from MCNP5 calculations can be output using numerous flexible tallies: surface current and flux, volume flux, point or ring detectors, particle heating, fission heating, pulse height tally for energy or charge deposition, mesh tallies, and radiography tallies

  • The consensus values for anisotropy function and radial dose function for most source models are mostly selected from Monte Carlo results that spanned the required range of radial distances and angles, and had sufficiently fine spacing to make the interpolation between points accurate

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Summary

Introduction

The isotopes 125I and 103Pd are frequently used in low-dose rate (LDR) brachytherapy sources. The IR06-103Pd dosimetric data have been compared with data for other 103Pd commercial sources

Materials and Methods
Monte Carlo evaluation
Results & DISCUSSION
Method
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