Response of SOI microdosimeter in fast neutron beams: experiment and Monte Carlo simulations |
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| Affiliation: | 1. Centre for Medical Radiation Physics, University of Wollongong, Wollongong, Australia;2. iThemba Laboratory for Accelerator Based Sciences, Cape Town, South Africa;3. European Spallation Source (ESS), Lund, Sweden;4. Department of Physics, Thin Film Physics Division, Linköping University, Sweden;1. School of Chemistry and Physics, Faulty of Science, Queensland Univeristy of Technology, 2 George Street, Brisbane, QLD 4000, Australia;2. Greenslopes Private Hospital, Ramsay Health Care, Newdegate Street, Greenslopes, Brisbane, QLD 4120, Australia;3. School of Clinical Sciences, Faculty of Health, Queensland University of Technology, 2 George Street, Brisbane, QLD 4000, Australia;4. Centre for Biomedical Technologies (CBT), Queensland University of Technology, Brisbane, QLD 4000, Australia;5. QMIR Berghofer Medical Research Institute, 200 Herston Road, Herston, QLD 4006, Australia;1. Centre for Medical Radiation Physics, University of Wollongong, NSW 2522, Australia;2. NSTLI Nuclear Stewardship, Australian Nuclear Science and Technology Organization, Lucas Heights, NSW 2234, Australia;3. University Sains Malaysia, Pulau Penang, Malaysia;4. Dipartimento di Ingegneria Nucleare, Politecnico di Milano, 20133 Milano, Italy;5. Research Centre for Charge Particle Therapy, National Institute of Radiological Science, Chiba, Japan;6. University of New South Wales, Sydney, NSW 2052, Australia;1. Osaka Medical College, Kansai BNCT Medical Center, Osaka, Japan;2. Kyoto University, Institute for Integrated Radiation and Nuclear Science, Osaka, Japan;3. Osaka Medical College Hospital, Central Department of Radiology, Osaka, Japan |
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| Abstract: | In this study, Monte Carlo codes, Geant4 and MCNP6, were used to characterize the fast neutron therapeutic beam produced at iThemba LABS in South Africa. Experimental and simulation results were compared using the latest generation of Silicon on Insulator (SOI) microdosimeters from the Centre for Medical Radiation Physics (CMRP). Geant4 and MCNP6 were able to successfully model the neutron gantry and simulate the expected neutron energy spectrum produced from the reaction by protons bombarding a 9Be target. The neutron beam was simulated in a water phantom and its characteristics recorded by the silicon microdosimeters; bare and covered by a 10B enriched boron carbide converter, at different positions. The microdosimetric quantities calculated using Geant4 and MCNP6 are in agreement with experimental measurements. The thermal neutron sensitivity and production of 10B capture products in the p+ boron-implanted dopant regions of the Bridge microdosimeter is investigated. The obtained results are useful for the future development of dedicated SOI microdosimeters for Boron Neutron Capture Therapy (BNCT). This paper provides a benchmark comparison of Geant4 and MCNP6 capabilities in the context of further applications of these codes for neutron microdosimetry. |
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| Keywords: | BNCT FNT solid-state microdosimetry Geant4 MCNP accelerator |
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