Dosimetric aspects of 103Pd radioactive stent source
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M. Sadeghi
Abstract
This study aims to determine AAPM TG-60 dosimetric quantities in regions surrounding the 103Pd stent wall by MCNP5 Monte Carlo code. The Palmaz-Schatz stent was modeled by a hollow cylinder of 17.89mm length (2mm diameter) with net surface very similar to real stent. The Dose deposited per photon (Gy), relative dose, Anisotropy function, F(r,θ), and radial dose function, gL(r), were described at AAPM TG-60 protocol were generated from these values and listed in tabular format. For benchmarking, the relative dose values were verified with TG-43 and EGS4 code results at identical conditions, relative to the radial distances from surface of the stent. There were noticeable results. These physical dosimetric parameters can be used in future treatment planning systems for IVBT.
Kurzfassung
Ziel dieser Arbeit war die Bestimmung dosimetrischer Größen in der Umgebung von 103Pd Stents gemäß den AAPM TG-60-Empfehlungen mit Hilfe des MCNP5 Monte Carlo Rechencodes. Der Palmaz-Schatz Stent wurde dabei modelliert durch einen Hohlzylinder von 17.89mm Länge (2mm Durchmesser) mit einer Netzoberfläche ähnlich der des realen Stents. Die pro Photon erzeugte Dosis (Gy), die relative Dosis, die Anisotropiefunktion, F(r,θ), und die radiale Dosisfunktion, gL(r), wurden wie im AAPM TG-60-Protokoll beschrieben aus diesen Werten erzeugt und tabellarisch dargestellt. Zu Benchmarkingzwecken wurden die relativen Dosiswerte verifiziert mit TG-43 und EGS4 Rechenergebnissen bei gleichen Bedingungen, relative zur radialen Entfernung von der Stentoberfläche. Die Ergebnisse sind bemerkenswert. Die dosimetrischen Parameters können bei zukünftigen Therapieplanungssystemen für IVBT verwendet werden.
References
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© 2012, Carl Hanser Verlag, München
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Articles in the same Issue
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Technical Contributions/Fachbeiträge
- Simulation of HALDEN IFA-650 loss-of-coolant accidents tests with TRACE
- On the evaluation of a fuel assembly design by means of uncertainty and sensitivity measures
- Best estimate plus uncertainty analysis of LBLOCA for Indian PHWR
- Remarks on boiling water reactor stability analysis – part 1: theory and application of bifurcation analysis
- Upgrading (V)HTR fuel elements for generationIV goals by SiC encapsulation
- Investigation of the Ru-43LV fuel behaviour under LOCA conditions in a CANDU reactor
- PCA-based ANN approach to leak classification in the main pipes of VVER-1000
- Analytical investigation of the properties of the neutron noise induced by vibrating absorber and fuel rods
- Diffusion approximation for certain scattering parameters of the Anli-Güngör phase function
- Calculation of beta induced Bremsstrahlung exposure from therapeutic radionuclide 198Au in tissues, DNA and RNA
- Dosimetric aspects of 103Pd radioactive stent source
- Radiological significance of coal, slag and fly ash samples from the Eastern Black Sea region
