
doi: 10.1093/rpd/nch145
pmid: 15353754
The paper presents results of the numerical modelling of the fission-converter-based epithermal neutron source designed for the boron neutron capture therapy (BNCT) facility to be located at the Polish research nuclear reactor MARIA at Swierk. The unique design of the fission converter has been proposed due to a specific geometrical surrounding of the reactor. The filter/moderator arrangement has been optimised to moderate fission neutrons to epithermal energies and to remove both fast neutrons and photons from the therapeutic beam. The selected filter/moderator set-up ensures both high epithermal neutron flux and suitably low level of beam contamination. Photons originating from the reactor core are almost eliminated what is the exceptional advantage of the proposed design. It yields one order of magnitude lower gamma radiation dose than the maximum allowed dose in such a type of therapeutic facility. The MCNP code has been used for the computations.
Neutrons, Quality Control, Reproducibility of Results, Boron Neutron Capture Therapy, Radiotherapy Dosage, Equipment Design, Models, Theoretical, Risk Assessment, Sensitivity and Specificity, Equipment Failure Analysis, Risk Factors, Computer-Aided Design, Humans, Scattering, Radiation, Computer Simulation, Linear Energy Transfer, Radiometry, Algorithms, Relative Biological Effectiveness
Neutrons, Quality Control, Reproducibility of Results, Boron Neutron Capture Therapy, Radiotherapy Dosage, Equipment Design, Models, Theoretical, Risk Assessment, Sensitivity and Specificity, Equipment Failure Analysis, Risk Factors, Computer-Aided Design, Humans, Scattering, Radiation, Computer Simulation, Linear Energy Transfer, Radiometry, Algorithms, Relative Biological Effectiveness
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