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A Monte Carlo dose engine for fast neutron therapy and boron neutron capture therapy for matRad.
Biomed. Phys. Eng. Express 11:065023 (2025)
Objective:The purpose of the work presented here was to enable easy access to Monte Carlo dose calculation for both fast neutron therapy and boron neutron capture therapy for research purposes. The dose calculation approach was especially intended to hold high customization potential for individual user applications.Approach:The dose engine is based on the Monte Carlo code MCNP. It is integrated into the MATLAB-based open source research treatment planning software matRad as modular component.Main results:Total dose calculation is enabled for both fast neutron therapy and boron neutron capture therapy on patient CT data. The evaluation of the dose distribution is possible using the matRad graphical user interface and dose volume histograms. Customization options are provided for advanced users.Significance:The open source treatment planning software allows easy access to highly accurate Monte Carlo dose calculation for research projects.
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Publication type
Article: Journal article
Document type
Scientific Article
Keywords
Mcnp Dose Calculation ; Monte Carlo Dose Calculation ; Boron Neutron Capture Therapy ; Fast Fission Neutron Therapy ; Fission Neutron Source ; Neutron Dose Calculation; Radiotherapy; Optimization; Medapp
ISSN (print) / ISBN
2057-1976
e-ISSN
2057-1976
Quellenangaben
Volume: 11,
Issue: 6,
Article Number: 065023
Publisher
Institute of Physics Publishing (IOP)
Publishing Place
Bristol
Reviewing status
Peer reviewed
Institute(s)
Institute of Radiation Medicine (IRM)
Grants
Deutsche Forschungsgemeinschaft
Bundesministerium fr Forschung, Technologie und Raumfahrt
Bundesministerium fr Forschung, Technologie und Raumfahrt