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The relative biological effectiveness (RBE) of neutrons in neutron beams is crucial for the clinical implementation of accelerator-based boron neutron capture therapy (BNCT) systems. The RBE was quantified by comparing the doses required to achieve a 10 % cell survival fraction (D10) between reference radiation (photons) and neutrons. However, in accelerator-based BNCT, the neutron beam includes not only neutrons but also contaminating gamma rays, making it essential to calculate the RBE of neutrons while accounting for the gamma-ray dose. The RBE of neutrons was calculated using a recently proposed method, which assumes that the interaction between neutrons and contaminating gamma rays is independent, and this was compared with the conventional method, which assumes that the interactions are not independent. These calculations were conducted in an accelerator-based BNCT system with a solid-state lithium target. A comparison was also performed by varying the representative beam parameters to validate the RBE values. Additionally, the photon isoeffective dose was implemented and compared with the RBE-weighted dose calculated from the two RBE values. Four cell lines (SAS, SCCVII, U87-MG, and NB1RGB) were used to assess the cell survival fraction (SF). The SF curves for neutrons and photons were derived using linear and linear-quadratic models, respectively, to calculate D10. For the four cell lines, the mean RBE value calculated using the conventional method was 1.9 (RBE1), while that calculated using the recent method was 2.0 (RBE2). Furthermore, when the photon isoeffective dose was calculated, it closely matched the RBE-weighted doses obtained using RBE1 and RBE2 from the four cell lines. This study also examined the impact of varying the ratio of contaminating gamma rays to neutron doses, a representative beam parameter, on RBE1 and RBE2. The RBE2 value remained independent of the ratio, whereas the RBE1 value increased with rising gamma-ray contamination. However, the two RBE values was comparable when the system was adequately designed for clinical BNCT use. Therefore, this study suggests that comparing the RBE values derived from the two different methods can confirm not only the validity of the RBE but also the representative beam parameters in accelerator-based BNCT.
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http://dx.doi.org/10.1016/j.apradiso.2025.111834 | DOI Listing |
Appl Radiat Isot
August 2025
Kansai BNCT Medical Center, Osaka Medical and Pharmaceutical University, Takatsuki, Osaka, Japan.
Purpose: The Phase II clinical trial (JG002) investigating accelerator-based boron neutron capture therapy (AB-BNCT) using a cyclotron-based epithermal neutron source for recurrent malignant gliomas has since concluded. The trial demonstrated favorable survival outcomes during the 1-year evaluation period defined in the protocol for patients with recurrent glioblastoma, a population with notoriously poor prognosis. Follow-up was originally limited to up to two years.
View Article and Find Full Text PDFSci Rep
August 2025
Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai, 201800, People's Republic of China.
In modern Boron neutron capture therapy (BNCT) treatment planning, F-BPA (F-boronophenylalanine) PET (positron emission tomography) imaging is used to assess boron uptake and guide accurate dose delivery. This study evaluates the geometric and dosimetric differences between target volumes defined by MRI (magnetic resonance imaging) and PET images in accelerator-based BNCT using the NeuPex system. The GTV (gross tumor volume) was defined based on MRI (GTV) and PET images with SUV thresholds of 2.
View Article and Find Full Text PDFAppl Radiat Isot
August 2025
Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, PR China. Electronic address:
This study introduces NeuMANTA (Multifunctional Arithmetic for Neutron Transportation Analysis), a dedicated treatment planning system (TPS) developed for accelerator-based boron neutron capture therapy (AB-BNCT). NeuMANTA integrates Monte Carlo-based dose calculation with modular workflow management to enable full-cycle support from imaging to post-treatment verification. Powered by the BNCT-specific COMPASS (COMpact PArticle Simulation System) engine, the system achieves dosimetric accuracy comparable to MCNP while reducing computation time by 2.
View Article and Find Full Text PDFSci Rep
August 2025
Department of Radiotherapy, Renmin Hospital of Wuhan University, Wuhan, 430060, China.
This study investigated the impact of nuclear reaction cross-sections data from various nuclear data libraries on neutron parameters in Monte Carlo simulations using the PHITS code for accelerator-based BNCT (AB-BNCT). Specifically, it evaluated the effect of different proton data libraries-ENDF/B VII.1, ENDF/B VIII.
View Article and Find Full Text PDFJ Appl Clin Med Phys
August 2025
Kansai BNCT Medical Center, Osaka Medical and Pharmaceutical University, Osaka, Japan.
Background: Currently, the metal foil activation method is routinely used to measure the neutron output of an accelerator-based neutron source designed for clinical Boron neutron capture therapy (BNCT). Although this method is well established and has been primarily utilized since the nuclear reactor BNCT era, the process is labour-intensive and not well-suited for a busy hospital environment performing routine patient treatment. A replacement neutron detector system that is simple to use and can measure the neutron output in real-time is necessary.
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