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Dosimetry for gadolinium neutron capture therapy (GdNCT)
Uppsala University, Medicinska vetenskapsområdet, Faculty of Medicine, Department of Oncology, Radiology and Clinical Immunology.
Manuscript (Other academic)
URN: urn:nbn:se:uu:diva-97528OAI: oai:DiVA.org:uu-97528DiVA: diva2:172512
Available from: 2008-09-19 Created: 2008-09-19 Last updated: 2010-01-13Bibliographically approved
In thesis
1. Dosimetry Studies of Different Radiotherapy Applications using Monte Carlo Radiation Transport Calculations
Open this publication in new window or tab >>Dosimetry Studies of Different Radiotherapy Applications using Monte Carlo Radiation Transport Calculations
2008 (English)Doctoral thesis, comprehensive summary (Other academic)
Abstract [en]

Developing radiation delivery systems for optimisation of absorbed dose to the target without normal tissue toxicity requires advanced calculations for transport of radiation. In this thesis absorbed dose and fluence in different radiotherapy applications were calculated by using Monte Carlo (MC) simulations.

In paper I-III external neutron activation of gadolinium (Gd) for intravascular brachytherapy (GdNCB) and tumour therapy (GdNCT) was investigated. MC codes MCNP and GEANT4 were compared. MCNP was chosen for neutron capture reaction calculations. Gd neutron capture reaction includes both very short range (Auger electrons) and long range (IC electrons and gamma) products. In GdNCB the high-energetic gamma gives an almost flat absorbed dose delivery pattern, up to 4 mm around the stent. Dose distribution at the edges and inside the stent may prevent stent edge and in-stent restenosis. For GdNCT the absorbed dose from prompt gamma will dominate over the dose from IC and Auger electrons in an in vivo situation. The absorbed dose from IC electrons will enhance the total absorbed dose in the tumours and contribute to the cell killing.

In paper IV a model for calculation of inter-cluster cross-fire radiation dose from β-emitting radionuclides in a breast cancer model was developed. GEANT4 was used for obtaining absorbed dose. The dose internally in cells binding the isotope (self-dose) increased with decreasing β-energy except for the radionuclides with substantial amounts of conversion electrons and Auger electrons. An effective therapy approach may be a combination of radionuclides where the high self-dose from nuclides with low β-energy should be combined with the inter-cell cluster cross-fire dose from high energy β-particles.

In paper V MC simulations using correlated sampling together with importance sampling were used to calculate spectra perturbations in detector volumes caused by the detector silicon chip and its encapsulation. Penelope and EGSnrc were used and yielded similar results. The low energy part of the electron spectrum increased but to a less extent if the silicon detector was encapsulated in low z-materials.

Place, publisher, year, edition, pages
Uppsala: Universitetsbiblioteket, 2008. 49 p.
Digital Comprehensive Summaries of Uppsala Dissertations from the Faculty of Medicine, ISSN 1651-6206 ; 375
External Beam Radiotherapy, Gadolinium Neutron Capture Therapy, Gadolinium Neutron Capture Brachytherapy, Targeted Radionuclide therapy, Detector Response Modelling, Monte Carlo Simulation.
National Category
Radiology, Nuclear Medicine and Medical Imaging
urn:nbn:se:uu:diva-9277 (URN)978-91-554-7279-5 (ISBN)
Public defence
2008-10-11, Fåhreussalen, C5, Rudbecklaboratoriet, Dag Hammarskjölds väg 20, Uppsala, 09:15
Available from: 2008-09-19 Created: 2008-09-19Bibliographically approved

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