Neutron spectrometry of the 9Be(d (1.45 MeV), n)10B reaction for accelerator-based BNCT

Capoulat, M.E.; Sauzet, N.; Valda, A.A.; Gagetti, Leonardo; Guillaudin, O.; Lebreton, L.; Maire, D.; Mastinu, P.; Praena, J.; Riffard, Q.; Tampón, Benjamín; Santos, D.; Kreiner, Andrés J.

doi:10.1016/j.nimb.2019.03.005

Cited by 10 publications

(9 citation statements)

References 26 publications

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“…This ability to provide polyenergetic neutron spectrum has already been applied to characterize the angular distribution of fast neutrons produced in a nuclear reaction proposed for a radiotherapy called Accelerator-Based Boron Neutron Capture Therapy (AB-BNCT) [13]. We have recently demonstrated the interesting active phantom application for BNCT (Boron Neutron Capture Therapy) and PFBT (Proton Fusion Boron Theapy) profiting of the calibration device.…”

Section: Discussionmentioning

confidence: 99%

Neutron spectroscopy from 1 to 15 MeV with Mimac-FastN, a mobile and directional fast neutron spectrometer and an active phantom for BNCT and PFBT

et al. 2020

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In the frame of direct dark matter search, the fast neutrons producing elastic collisions on the nuclei of the active volume are the ultimate background. The MIMAC (MIcro-tpc MAtrix Chambers) project has developed a directional detector providing the directional signature to discriminate them from the searched events based on 3D nuclear tracks reconstruction. The MIMAC team of the LPSC has adapted one MIMAC chamber as a mobile fast neutron spectrometer, the Mimac-FastN detector, having a wide neutron energy range (10 keV – 600 MeV) working with different gas mixtures and pressures. This presentation will be focused on the MeV range with 4He + 5% CO2 gas mixture at 700 mbar. A boron coating inside the active volume used for calibration purpose opens the possibility to use the active volume as an active phantom for Boron Neutron Capture Therapy (BNCT) and Proton Fusion Boron Therapy (PFBT).

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Section: Discussionmentioning

confidence: 99%

Neutron spectroscopy from 1 to 15 MeV with Mimac-FastN, a mobile and directional fast neutron spectrometer and an active phantom for BNCT and PFBT

et al. 2020

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“…The energy and angle distribution of the generated neutrons for a 9 μm thick thin target was measured by Capoulat et al and is given in the figure 4 of Capoulat et al (2019). This distribution, which shows a maximum below ∼0.4 MeV whatever the angle and a tail of fast neutrons up to ∼6 MeV, is rigorously implemented in the transport code used for this study, MCNP 6, by using the functionalities of its SDEF card (Goorley et al 2012).…”

Section: Neutron Sourcementioning

confidence: 99%

Heavy-water-based moderator design for an AB-BNCT unit using a topology optimization algorithm

Chabod¹,

Giraud²,

Hervé³

et al. 2022

Phys. Med. Biol.

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Objective. The design of neutron moderators for BNCT treatment units currently relies on parametric approaches, which yield quality results but are ultimately limited by human imagination. Efficient but non-intuitive design solutions may thus be missed out. This limitation needs to be addressed. Approach. To overcome this limitation, we propose to use a topology optimization algorithm coupled with a state-of-the-art Monte-Carlo transport code. This approach recently proved capable of finding complex optimal configurations of particle propagators with limited human intervention. Main results. In this study, we apply this algorithmic solution to optimize some heavy-water neutron moderators for a specific AB-BNCT treatment unit. The moderators thus generated are compact yet succeed in limiting the exposure of patient’s healthy tissues to levels below recommended limits. They present subtle, original geometries inaccessible to standard parametric approaches or human intuition. Significance. This approach could be used to automatically fit the design of a BNCT moderator to the location and shape of the tumor or to the morphology of the patient to be treated, opening a path for more targeted BNCT treatment.

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“…Neutron sources are used in many domains such as isotopes production, non-destructive imaging, subsurface exploration, silicon transmutation doping, and, in the medical, domain Neutron Capture Therapies profiting of the huge 10 B neutron capture cross section [1][2] producing an energetic alpha particle and Li nuclear recoil with a 478 keV gamma ray in 94% of cases [fig 1] Unlike nuclear reactors, accelerator-based neutron sources appear like safe, compact and cheap solutions to produce a high neutron flux [3]. This is especially true for Neutron Capture Therapies, which require the highest thermal neutron flux produced by the smallest compact neutron source suitable to sit in a hospital.…”

Section: Contextmentioning

confidence: 99%

Development of a regenerated Beryllium target and a thermal test facility for Compact Accelerator-based Neutron Sources

et al. 2020

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Recently, the possibility to use compact accelerators coupled to high current ion sources for the production of intense low energy proton or deuteron beams has motivated many research laboratories to develop accelerator based neutrons sources for several purposes, including Neutron Capture Therapy (NCT). The NCT needs a high flux, about 10 9 n.cm-2.s-1, of thermal neutrons (E<10 keV) at the tumour site. Up to now, the NCT required neutron flux was mainly delivered by nuclear reactors. However, the production of such neutron flux is now possible using proton or deuteron beams on specific targets able to stand a high pow er (~15- 30 kW) on a small area (~10 cm2). This specific target design, materials and supports, has to cope with extreme physical constraints . The LPSC team has conceived an original solution formed by a thin (8 μm) rotating beryllium target depos ited on a graphite wheel and coupled with a beryllium sputtering device for periodic 9Be layer restoration. By means of 9Be (d,n) 10B nuclear reaction, this target irradiated by a 10- -20 mA deuteron beam (1.45 MeV) should produce the required neutron flux. In order to validate the target design of the neutron flux production and the beryllium target thermal capabilities, we built a 30 cm diameter rotating Beryllium target prototype and a compact electron beam line able to deliver a power density of 3kW/cm2.

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Neutron spectrometry of the 9Be(d (1.45 MeV), n)10B reaction for accelerator-based BNCT

Cited by 10 publications

References 26 publications

Neutron spectroscopy from 1 to 15 MeV with Mimac-FastN, a mobile and directional fast neutron spectrometer and an active phantom for BNCT and PFBT

Neutron spectroscopy from 1 to 15 MeV with Mimac-FastN, a mobile and directional fast neutron spectrometer and an active phantom for BNCT and PFBT

Heavy-water-based moderator design for an AB-BNCT unit using a topology optimization algorithm

Development of a regenerated Beryllium target and a thermal test facility for Compact Accelerator-based Neutron Sources

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Neutron spectrometry of the 9Be(d (1.45 MeV), n)10B reaction for accelerator-based BNCT

Cited by 10 publications

References 26 publications

Neutron spectroscopy from 1 to 15 MeV with Mimac-FastN, a mobile and directional fast neutron spectrometer and an active phantom for BNCT and PFBT

Neutron spectroscopy from 1 to 15 MeV with Mimac-FastN, a mobile and directional fast neutron spectrometer and an active phantom for BNCT and PFBT

Heavy-water-based moderator design for an AB-BNCT unit using a topology optimization algorithm

Development of a regenerated Beryllium target and a thermal test facility for Compact Accelerator-based Neutron Sources

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Product

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Neutron spectrometry of the 9Be(d (1.45 MeV), n)10B reaction for accelerator-based BNCT