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Matsuya, Yusuke; Sato, Tatsuhiko; Kusumoto, Tamon*; Yachi, Yoshie*; Seino, Ryosuke*; Miwa, Misako*; Ishikawa, Masayori*; Matsuyama, Shigeo*; Fukunaga, Hisanori*
Scientific Reports (Internet), 14, p.16696_1 - 16696_14, 2024/07
Times Cited Count：2 Percentile：84.90(Multidisciplinary Sciences)Boron neutron capture therapy (BNCT) is a unique radiotherapy to selectively eradicate tumor cells using boron compounds (e.g., 4-borono-L-phenylalanine [BPA]) that are heterogeneously taken up at the cellular level. However, the impacts of tempo-spatial heterogenicity on cell killing remain unclear. With the technical combination of radiation track detector, cell cycle analysis, and biophysical simulations, we demonstrated the cell cycle-dependent heterogenicity of BPA uptake and following biological impacts of 
B(n, 
)
Li reactions in HeLa cells expressing Fluorescent Ubiquitination-based Cell Cycle Indicators (FUCCI), as well as its modification effects of polyvinyl alcohol (PVA). As a result, we revealed that the intracellular BPA concentration in the S/G2/M phase was higher than that in the G1/S phase and that PVA modified the cell cycle dependence. Further, these findings lead to the development of the first BPA-PVA-based model for predicting BNCT treatment effects. These outcomes may contribute to more precision of therapeutic efficacy, when BNCT is combined with PVA and/or cell cycle-specific anticancer agents.
Matsuya, Yusuke; Kusumoto, Tamon*; Yachi, Yoshie*; Hirata, Yuho; Miwa, Misako*; Ishikawa, Masayori*; Date, Hiroyuki*; Iwamoto, Yosuke; Matsuyama, Shigeo*; Fukunaga, Hisanori*
AIP Advances (Internet), 12(2), p.025013_1 - 025013_9, 2022/02
Times Cited Count：7 Percentile：58.79(Nanoscience & Nanotechnology)Boron Neutron Capture Therapy (BNCT) is a radiation therapy, which can selectively eradicate solid tumors by -particles and Li ions generated through the nuclear reaction between thermal neutron and B in tumor cells. With the development of accelerator-based neutron sources that can be installed in medical institutions, accelerator-based boron neutron capture therapy is expected to become available at several medical institutes around the world in the near future. Lithium is one of the targets that can produce thermal neutrons from the Li(p,n)Be near-threshold reaction. Particle and Heavy Ion Transport code System (PHITS) is a general-purpose Monte Carlo code, which can simulate a variety of diverse particle types and nuclear reactions. The latest PHITS code enables simulating the generation of neutrons from the Li(p,n)Be reactions by using Japanese Evaluated Nuclear Data Library (JENDL-4.0/HE). In this study, we evaluated the neutron fluence using the PHITS code by comparing it to reference data. The subsequent neutron transport simulations were also performed to evaluate the boron trifluoride (BF
) detector responses and the recoiled proton fluence detected by a CR-39 plastic detector. As a result, these comparative studies confirmed that the PHITS code can accurately simulate neutrons generated from an accelerator using a Li target. The PHITS code has a significant potential for contributing to more precise evaluating accelerator-based neutron fields and understandings of therapeutic effects of BNCT.
Miyazaki, Yasunori; Sano, Yuichi; Takeuchi, Masayuki; Arai, Tsuyoshi*; Kim, S.-Y.*; Wu, H.*; Miwa, Misako*; Matsuyama, Shigeo*
no journal, ,
Separation of minor actinides (MA; Am, Cm) is social demand to reduce the volume and toxicity of radioactive waste generated by spent nuclear fuel reprocessing. We have proposed extraction chromatography that employs the TEHDGA-impregnated adsorbent in a separation column. From the previous study, MA recovery from the real radioactive waste liquid was achieved, and a flowsheet study is continued to improve the product purity (or decontamination coefficient). On the other hand, we are also investigating the decomposition and reuse of spent adsorbent. In this presentation, both of the degradability of the adsorbent by the Fenton reaction and the reusability of the re-impregnated adsorbent from the batch-wise adsorption test results are reported by the element distribution by micro-PIXE analysis.
