Experimental validation of a spectroscopic gamma-ray detector based on a LaBr3 scintillator towards real-time dose monitoring in BNCT

Caracciolo, Anita; Vita, Davide Di; Buonanno, Luca; Carminati, Marco; Protti, Nicoletta; Altieri, S.; Pola, A.; Bortot, D.; Fiorini, C.

doi:10.1016/j.nima.2022.167409

Cited by 11 publications

(14 citation statements)

References 18 publications

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“…Due to recent advances in manufacturing technologies, silicon photomultipliers (SiPMs) combine high performance with the practical advantages of solid-state technology that includes the following: low operating voltage, excellent temperature stability, robustness, compactness, output uniformity, and low cost. Therefore, SiPMs have been increasingly used in gamma ray detection [56][57][58][59] and medical imaging [50,51].…”

Section: Methodsmentioning

confidence: 99%

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Compact pixelated scintillator detector investigation for gamma ray detection

Wang,

Wu,

et al. 2024

Eng. Res. Express

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A scintillator is a luminescent material that converts high-energy photons into visible light and is widely used in medical imaging. The energy resolution, detection efficiency and position measurement of pixelated scintillators coupled to a SiPM were investigated via two kinds of detectors. The goal of this manuscript was to accurately measure the gamma source position through spectrum analysis in selection of energy windows for characteristic gamma lines. In this manuscript, scintillators were effectively manufactured and encapsulated before testing, especially for the easily deliquescent LaBr3. The compact front-end electronic prototype modules with 2×2 array SiPMs in stacked form and 1×10 array SiPMs in parallel form were developed for gamma ray energy resolution and efficiency measurements with a radioactive source of 22Na, which had two energy gamma lines at 511 keV and 1274 keV.

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Section: Methodsmentioning

confidence: 99%

“…Therefore, to resolve the boron photopeak at 478 keV, a detector with good energy resolution was needed [49]. Thus, the BeNEdiCTE module was developed based on a cylindrical 2-inch LaBr 3 scintillator crystal with high energy resolution (<3% at 662 keV) [50,51].…”

Section: Introductionmentioning

confidence: 99%

Compact pixelated scintillator detector investigation for gamma ray detection

Wang,

Wu,

et al. 2024

Eng. Res. Express

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“…The gamma-ray detector we developed is called BeNEdiCTE (Boron NEutron CapTurE) module. It has already been used to perform BNCT measurements with the TRIGA Mark II research nuclear reactor of Pavia University, as described in [7]. The first version was based on a cylindrical LaBr 3 (Ce+Sr) scintillator crystal of 5 cm diameter and thickness, read out by a matrix of 64 SiPMs and four custom ASICs.…”

Section: System Architecturementioning

confidence: 99%

“…Boron Neutron Capture Therapy (BNCT) is a targeted radiotherapy technique in which patients are administered a 10 B-enriched compound that is preferentially taken up by tumor cells and are then irradiated with a thermal neutron beam. Energetic charged particles released by 10 B(n,𝛼) 7 Li capture reaction produce localized damage to the tumor cells, sparing healthy tissues [1]. In recent years BNCT has re-gained more attention thanks to the development of accelerator-based BNCT facilities, already installed in Japan and under construction or planned also in Europe [2].…”

Section: Introductionmentioning

confidence: 99%

“…The system has an excellent energy resolution (< 3% at 662 keV), in principle adequate to separate the 478 keV peak from other adjacent lines, mainly the 511 keV due to annihilation photons [6]. A recent proof-of-principle prototype, based on a cylindrical LaBr 3 (Ce+Sr) scintillator crystal of 5 cm diameter and thickness, has successfully demonstrated its capability to identify the 10 B compounds when irradiating borated vials with thermal neutrons at the LENA (Laboratory of Applied Nuclear Energy) reactor in Pavia [7]. However, a background signal at 478 keV was detected even with no boron inside the irradiated vial, indicating a possible neutron activation of the detector itself.…”

Section: Introductionmentioning

confidence: 99%

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Study of the thermal neutron activation of a gamma-ray detector for BNCT dose monitoring

Colombo,

Caracciolo,

Mazzucconi

et al. 2024

J. Inst.

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We present a study on the neutron activation of a gamma-ray detector for a BNCT-SPECT dose imaging system. The detector is based on a LaBr3(Ce+Sr) scintillator crystal, coupled with a matrix of Silicon Photomultipliers (SiPMs), read by a dedicated electronics system. This detector has successfully demonstrated to be capable to identify the 10B compounds when irradiating borated vials with thermal neutrons. However, a background signal around 478 keV was detected, suggesting the activation of the detector itself. This study aims to determine the origin of this background signal by simulating the two main parts of the detector, which are the crystal and electronic boards, in order to assess their contribution to the background signal. The results of the FLUKA simulations show that the neutron capture reactions on both the crystal and electronic boards cause a relevant background nearby the BNCT signal, thereby limiting the detector's sensitivity. To address this issue, a customized cadmium shielding has been developed. This solution was tested at the TRIGA Mark II research nuclear reactor of Pavia University, where experimental measurements and corresponding FLUKA simulations proved its effectiveness.

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