Characterisation of the TAPIRO BNCT epithermal facility
Copyright policy )Characterisation of the TAPIRO BNCT epithermal facility
A collimated epithermal beam for boron neutron capture therapy (BNCT) research has been designed and built at the TAPIRO fast research reactor. A complete experimental characterisation of the radiation field in the irradiation chamber has been performed, to verify agreement with IAEA requirements. Slow neutron fluxes have been measured by means of an activation technique and with thermoluminescent detectors (TLDs). The fast neutron dose has been determined with gel dosemeters, while the fast neutron spectrum has been acquired by means of a neutron spectrometer based on superheated drop detectors. The gamma-dose has been measured with gel dosemeters and TLDs. For an independent verification of the experimental results, fluxes, doses and neutron spectra have been calculated with Monte Carlo simulations using the codes MCNP4B and MCNPX_2.1.5 with the direct statistical approach (DSA). The results obtained confirm that the epithermal beams achievable at TAPIRO are of suitable quality for BNCT purposes.
- University of Milan Italy
Neutrons, Radiotherapy Planning, Computer-Assisted, Reproducibility of Results, Boron Neutron Capture Therapy, Radiotherapy Dosage, Equipment Design, Risk Assessment, Sensitivity and Specificity, Equipment Failure Analysis, Radiation Protection, Italy, Gamma Rays, Nuclear Reactors, Body Burden, Humans, dosimetry; fission reactor monitoring; fission research reactors; gamma-ray detection; Monte Carlo methods; neutron capture therapy; neutron detection; neutron flux; neutron spectrometers; nuclear engineering computing; thermoluminescent dosimeters, Radiometry, Monte Carlo Method, Algorithms, Relative Biological Effectiveness
Neutrons, Radiotherapy Planning, Computer-Assisted, Reproducibility of Results, Boron Neutron Capture Therapy, Radiotherapy Dosage, Equipment Design, Risk Assessment, Sensitivity and Specificity, Equipment Failure Analysis, Radiation Protection, Italy, Gamma Rays, Nuclear Reactors, Body Burden, Humans, dosimetry; fission reactor monitoring; fission research reactors; gamma-ray detection; Monte Carlo methods; neutron capture therapy; neutron detection; neutron flux; neutron spectrometers; nuclear engineering computing; thermoluminescent dosimeters, Radiometry, Monte Carlo Method, Algorithms, Relative Biological Effectiveness
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