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Accurate gamma-ray dose measurement up to 10 MeV by glass dosimeter with a sensitivity control filter for BNCT.
Appl Radiat Isot
July 2024
Graduate School of Engineering, Osaka University, Yamada-oka 2-1, Suita, Osaka, 565-0871, Japan. Electronic address:
Glass dosimeters are very useful and convenient detection elements in radiation dosimetry. In this study, this glass dosimeter was applied to a BNCT treatment field. Boron Neutron Capture Therapy (BNCT) is a next-generation radiation therapy that can selectively kill only cancer cells.
View Article and Find Full Text PDFContribution of radioactive particles to the post-explosion exposure of atomic bomb survivors implied from their stable chromosome aberration rates.
Front Public Health
February 2024
Department of Radiation Biophysics, Research Institute for Radiation Biology and Medicine, Hiroshima University, Hiroshima, Japan.
Article Synopsis
- Nearly 80 years after the A-bomb was dropped, debates continue about the radiation doses received by survivors, particularly the neutron doses which are harder to evaluate accurately.
- Initial measurements of airborne kerma radiation are reliable, but post-explosion exposure from radioactive particles has been largely overlooked due to uncertainties in their behavior.
- Research indicates that indoor survivors may have experienced over 30% higher radiation exposure due to a higher production of neutron-induced radioactive particles in enclosed environments near the blast's hypocenter.
A dose calculation algorithm for boron neutron capture therapy using convolution/superposition method.
Appl Radiat Isot
January 2024
Program in Biomedical Radiation Sciences, Department of Transdisciplinary Studies, Graduate School of Convergence Science and Technology, Seoul National University, Seoul, Republic of Korea; Department of Applied Bioengineering, Graduate School of Convergence Science and Technology, Seoul National University, Seoul, Republic of Korea; Research Institute of Convergence Science, Seoul National University, Seoul, Republic of Korea; Advance Institutes of Convergence Technology, Seoul National University, Suwon, Republic of Korea. Electronic address:
The convolution/superposition (C/S) method originally designed for photon dose calculation was first applied for developing a treatment planning system for boron neutron capture therapy. The original concept of TEGMA (total energy generated per unit mass) was proposed to represent distinctive dose components from neutron reactions with the elements in the patient's tissue. First, neutron fluence distributions in a homogeneous brain phantom irradiated with an energy-groupwise pencil beam of 2.
View Article and Find Full Text PDFA comprehensive Monte Carlo simulation of the neutron response of multi-element microdosimetric detectors based on THick Gas Electron Multiplier.
Radiat Prot Dosimetry
October 2023
Department of Physics and Astronomy, McMaster University, Hamilton, ON L8S 4L8, Canada.
We present comprehensive Monte Carlo simulations for the neutron response of the multi-element microdosimetric detector based on THick Gas Electron Multiplier (THGEM). Simulations were carried out using the MCNP6.2 code to calculate the deposited energy spectrum in the gaseous sensitive volumes for three different configurations, 7 × 3, 19 × 5, 37 × 7 that occupy a cylindrical volume of 5-cm diameter by 5-cm length.
View Article and Find Full Text PDFInvestigation of the nuclear radiation interaction parameters of selected polymers for radiation therapy and dosimetry.
Radiol Phys Technol
June 2023
School of Advanced Sciences, KLE Technological University, Hubbali, 580031, India.
The mass attenuation coefficient (MAC), effective atomic number (Z), equivalent atomic number (Z), fast neutron removal cross-section (FNRCS), energy absorption buildup factor (EABF), mass-energy absorption coefficient (MenAC), relative kerma, and computed tomography (CT) numbers were calculated for the alginates, bisphenol A-glycidyl methacrylate (Bis-GMA), chitin, hyaluronic acid, polycaprolactone (PCL), polyether ether ketone (PEEK), polyethylene glycol (PEG), polyglycolide (PGA), polylactic acid (PLA), poly lacto-co-glycolic acid (PLGA), poly methyl methacrylate (PMMA), poly vinyl alcohol (PVA), polyvinylpyrrolidone (PVP), triethylene glycol dimethacrylate (TEGDMA), and urethane dimethacrylate (UDMA) polymers using the Phy-X/PSD and Py-MLBUF software. The total stopping power (TSP) of electrons, protons, and alpha particles was calculated for the selected polymers using the ESTAR, PSTAR, and ASTAR programs. The effective atomic number for absorption and charged particle (electron, proton, alpha, and carbon ion) interactions were estimated for the selected polymers using Phy-X/ZeXTRa software.
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