Development of a SPECT System Using CdTe-DSD for in Situ Dosimetry in Neutron Capture Therapy

Le résumé fourni par la source

We present the development of a real-time in situ dosimetry system for neutron capture therapy (NCT). NCT employs thermal neutrons to irradiate boron (BNCT) or gadolinium (Gd-NCT) agents that selectively accumulate in tumor cells, producing high-energy secondary particles that induce localized cell kill. To enable direct visualization and monitoring of these reactions, we integrated a cadmium-telluride doublesided strip detector (CdTe-DSD) with a 3D-printed tungsten parallel-hole collimator. The CdTe-DSD achieves an energy resolution of a few keV FWHM across 10-800 keV and a spatial resolution of$250 \mu \mathrm{m}$. This enables accurate measurement of the emission sites of 478 keV and$80 \text{keV} \gamma$-rays produced by the reactions of${ }^{10} \mathrm{B}$and${ }^{157} \text{Gd}$with thermal neutrons. At the Japan Research Reactor-3 (JRR-3), we imaged a$200 \mu \mathrm{L}$solution containing$1000 \text{ppm}{ }^{10} \mathrm{B}$and two$40 \mu \mathrm{m}$-thick rabbit liver tumor slices infused with${ }^{157}$Gd under neutron irradiation. Our imaging system reproduced the 8 mm circular projection of the${ }^{10} \mathrm{B}$image and visualized heterogeneous${ }^{157} \text{Gd}$distribution in the tumor slices. These results demonstrate the CdTe-DSD's potential for real-time dosimetry assessment and adaptive treatment planning in BNCT and Gd-NCT.

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