Ā I am an accomplished researcher and academic, currently pursuing a Ph.D. at the Graduate School of Engineering, Kyoto University. With a strong background in radiation therapy and dosimetry, my research has focused on radiation-induced secondary carcinogenesis and the development of precise Ī³-ray dosimetry methods for boron neutron capture therapy (BNCT). I have published several papers and presented at numerous conferences, contributing to advancements in proton therapy and BNCT. Currently, I am introducing the “nuBeam” accelerator-based BNCT system at Shonan Kamakura General Hospital and continue to innovate in the field of radiation dosimetry and cancer treatment technologies.
Education, Experience, and Academic Achievements š
I conducted research on radiation-induced secondary carcinogenesis during my master’s course at the Graduate School of Medicine, Hokkaido University, and presented my findings at an academic conference. Following my master’s, I joined the Minami-Tohoku Cancer Proton Therapy Center, where I published a paper on radiation-induced secondary carcinogenesis in children due to different proton therapy irradiation methods. Currently, I work at Shonan Kamakura General Hospital, where I am introducing the accelerator-based boron neutron capture therapy system “nuBeam” and presenting research on its initial evaluation at conferences and in scholarly papers. Additionally, I am conducting research on developing Ī³-ray dosimetry in neutron fields, which has been published and will be presented at an international conference. I am also pursuing a doctoral degree at the Graduate School of Engineering, Kyoto University, and will graduate this year.
Contributions to Research & Development, Innovations, and Extension Activities š§Ŗ
In the realm of boron neutron capture therapy (BNCT), the radiation emitted by the BNCT machine is directly linked to the patient dose. Therefore, accurately evaluating the gamma ray dose through measurement is crucial for introducing BNCT into clinical practice. Measurement methods for gamma ray doses in BNCT fields currently vary among facilities, necessitating a universally applicable and accurate method. In Japan, a custom-built thermoluminescent dosimeter (TLD) (Panasonic, UD-170LS) with beryllium oxide powder in a quartz glass tube is used for š¾ dose measurement, but it is no longer manufactured or commercially available. Consequently, I investigated a method combining a commercially available Mg2SiO4:Tb TLD (TOREC, TLD-MSO-S) with a 6LiF sintered capsule, verifying its efficacy for š¾ dose measurement in an accelerator-based (AB)-BNCT system.