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Endo, Akira
Annals of the ICRP, 52(4), p.5 - 7, 2024/12
In its Publication 155, International Commission on Radiological Protection (ICRP) has developed data on the Specific Absorbed Fraction (SAF) for reference males and females at ages of newborn, 1 year, 5 years, 10 years, and 15 years. The SAF represents the fraction of energy emitted within a source region which is absorbed in a target region per mass of the target region and is essential for calculating absorbed doses in organs or tissues for internal exposure. By combining the data of Publication 155 with the SAF data for reference adult males and females already published as Publication 133, an SAF dataset for the calculation of age-dependent dose coefficients for members of the public for environmental intakes of radionuclides has been completed. This, together with revised biokinetic models and nuclear decay data, means that the key building blocks for calculating new dose coefficients are in place. The outcome will soon be available in a series of ICRP Publications of Dose Coefficients for Intakes of Radionuclides by Members of the Public.
Martinez, N. E.*; Canoba, A.*; Donaher, S. E.*; Garnier-Laplace, J.*; Kinase, Sakae; Mayall, A.*; Stark, K.*; Whicker, J.*
Annals of the ICRP, 52, p.240 - 248, 2024/00
Sato, Tatsuhiko
Annals of the ICRP, 49(1_suppl.), p.185 - 192, 2020/12
The radiation environment in space is a complex mixture of particles of solar and galactic origin with a broad range of energies. For astronaut dose estimation, three sources must be considered, namely, galactic cosmic rays (GCR), trapped particles (TP), and solar energetic particles (SEP). More details about the radiation environment in space will be discussed at the symposium, together with the recent progresses on the space weather research for nowcasting and forecasting the astronaut doses due to SEP exposure.
Petoussi-Henss, N.*; Satoh, Daiki; Endo, Akira; Eckerman, K. F.*; Bolch, W. E.*; Hunt, J.*; Jansen, J. T. M.*; Kim, C. H.*; Lee, C.*; Saito, Kimiaki; et al.
Annals of the ICRP, 49(2), p.11 - 145, 2020/10
The age-dependent dose coefficients of organ equivalent doses and effective doses for the member of the public are required to estimate the external dose of the public exposed to radiations from radionuclides in the environment. For this purpose, a computational method to simulate the radiation fields of environmental photon and electron sources in the air, soil, and water has been developed using a particle transport code PHITS in the JAEA, and the organ equivalent doses have been calculated using the human models of newborns, 1-year-old, 5-years-old, 10-years-old, and 15-years-old children, and adults male and female provided by the ICRP. In addition, the nuclide-specific effective dose coefficients have been derived using the skin-dose data and nuclide-decay data provided by the Hanyang University and ICRP, respectively. The data of the dose coefficients are available for dose estimations of not only the Fukushima Daiichi nuclear accident but radiological emergencies which radionuclides are released to the environment.
Saito, Kimiaki
Annals of the ICRP, 49(2), p.7 - 9, 2020/10
no abstracts in English
Endo, Akira
Annals of the ICRP, 45(1_suppl.), p.178 - 187, 2016/06
The protection quantities, equivalent dose in an organ or tissue and effective dose, were developed by ICRP to allow quantification of the extent of exposure of the human body to ionizing radiation to be used for the implementation of the limitation and optimization principles. The body-related protection quantities are not measurable in practice. Therefore, ICRU developed a set of operational dose quantities for use in radiation measurements for external radiations that provide assessment of the protection quantities. ICRU has examined the rationale for operational quantities taking into account the changes in the definitions of the protection quantities in the ICRP 2007 Recommendations. The committee has investigated a set of alternative definitions for operational quantities different to the existing quantities. The major change in the currently favoured set of quantities is the redefinition of the operational quantities for area monitoring from being based on doses at a point in the ICRU sphere to ones based on particle fluence and the relationship to the protection quantities.
Endo, Akira; Sato, Tatsuhiko
Annals of the ICRP, 41(3-4), p.142 - 153, 2012/10
Radiation environment inside spacecrafts includes the primary radiation in space and secondary radiation produced by the interaction of the primary radiation with the equipment of the spacecrafts. Radiation fields inside astronauts are different from those outside them, because of the body-self shielding as well as the nuclear reactions occurring in the human body. Several computer codes have been developed to simulate the coupled transport of proton, heavy ions, and the secondary radiation produced in matter, and applied to space radiation protection: shielding design of spacecrafts, simulation of detector response, and analysis of organ doses in the human body. The presentation will focus on the methods and computer codes for radiation transport calculation of cosmic radiation, and their application to analysis of radiation fields inside spacecrafts, evaluation of organ doses and quality factors, and calculation of dose conversion coefficients using the ICRP reference phantoms.
