Preliminary design study of a simple neutron energy spectrometer using a CsI self-activation method for daily QA of accelerator-based BNCT

Proof-of-concept study on a water phantom-based neutron spectrometer: Experimental test with 252Cf and 241Am-Be sources

Boron neutron capture therapy (BNCT) is a promising cancer treatment that uses energetic ions released from 10B(n, α)7Li reactions. Accurate assessment of neutron energy spectra is important for simulation-based evaluation of neutron doses during BNCT. In this study, a proof-of-concept study was conducted for a neutron spectrometry technique that involves the use of a water phantom, which is commonly used for quality assurance in BNCT, as a moderator. The technique involves applying unfolding to the count rate distribution of the thermal neutron counter measured within the phantom to derive the energy spectrum. We performed experiments using a spherical 3He proportional counter in neutron fields generated by 252Cf and 241Am-Be sources. The results demonstrated that the spectrometer reasonably reproduced neutron spectra and showed the potential of using a water phantom as a moderator for such a technique.

Design and performance of an epithermal neutron flux detector using 55Mn(n,γ)56Mn reaction for BNCT

The measurement of the epithermal neutron (0.5 eV - 10 keV) flux of a boron neutron capture therapy (BNCT) treatment beam is a critical issue to its quality assessment and evaluation of the radiation dose to the treated patients. In this work, an activation detector using ⁵⁵Mn(n,γ)⁵⁶Mn reaction is designed by Monte Carlo simulations to measure the epithermal neutron flux of BNCT treatment beam. The detector is spherical and it has an absorber/moderator/absorber/manganese (Mn) foil arrangement from outside to inside. The activation material, i.e., Mn foil, is located at the geometrical center of the detector. After the design, the performance of the detector is evaluated by Monte Carlo simulations using the treatment neutron beams of operating reactor-based BNCT facilities. The results and related analysis indicate that the proposed detector will be efficiently applicable in the quality assessment of BNCT treatment beam and evaluation of the radiation dose to the treated patients.

Medical application of particle and heavy ion transport code system PHITS

The Particle and Heavy Ion Transport code System (PHITS) is a general-purpose Monte Carlo simulation code that has been applied in various areas of medical physics. These include application in different types of radiotherapy, shielding calculations, application to radiation biology, and research and development of medical tools. In this article, the useful features of PHITS are explained by referring to actual examples of various medical applications.