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Endo, Akira
JAEA-Research 2024-002, 90 Pages, 2024/05
JAEA-Research-2024-002.pdf:4.22MB
This report presents a comprehensive analysis of the relationship between three quantities used for area monitoring - ambient dose equivalent 
, maximum dose equivalent 
, and ambient dose 
- and effective dose for external irradiation by photons, neutrons, electrons, positrons, protons, muons, pions, and helium ions. For the analysis, calculations were performed using PHITS (Particle and Heavy Ion Transport code System) and the ICRU sphere. The analysis result shows that and can induce large differences in the estimation of effective dose over a wide energy range for various particle types covered by ICRP Publication 116 while can conservatively estimate effective dose within the acceptable range for area monitoring. In other words, and have limitations in estimating effective dose, and using is recommended as a more appropriate quantity for the purpose. This conclusion supports the proposal of ICRU Report 95 to use for estimating effective dose in various external exposure situations. The use of ambient dose is particularly important in situations where various types of radiation are encountered, such as the use of radiation in the medical and academic fields and exposure in aviation and can meet the evolving requirements of radiation monitoring for the expansion of the field of radiological protection.
Endo, Akira
Radiation Protection Dosimetry, 8 Pages, 2024/00
This study examines the relationship between ambient dose , ambient dose equivalent , and effective dose for external neutron irradiation over 163 operational spectra from different workplaces. The results show that provides a reasonable estimate with a controlled margin, even if overestimated, to assess effective dose compared with , which can lead to a significant overestimation or underestimation of effective dose depending on the neutron spectra. The results highlight the limitations of and the superiority of in estimating effective dose according to the requirements of the operational quantity, especially in environments with high-energy neutrons.
Sato, Rina; Sanada, Yukihisa; Yoshimura, Kazuya; Nakayama, Mariko*
JAEA-Review 2022-055, 42 Pages, 2023/01
JAEA-Review-2022-055.pdf:1.31MB
The evacuation order zones established after the accident at the Tokyo Electric Power Company's Fukushima Daiichi Nuclear Power Station have been reorganized according to the decrease in ambient dose equivalent rates and the decontamination progress. It has been decided to decontaminate the difficult-to-return zones and lift the evacuation order depending on the evacuee's intention of returning to the areas over the course of the 2020s. In order to consider the future of individual exposure dose assessment for residents for lifting of the evacuation orders, the methods and characteristics of the assessment that have been conducted after the accident using personal dosimeter measurements and simulations were systematically reviewed. This report summarized the results of the review.
Endo, Akira
Radiation Protection Dosimetry, 175(3), p.378 - 387, 2017/07
Times Cited Count：11 Percentile：71.88(Environmental Sciences)The International Commission on Radiation Units and Measurements (ICRU) has been discussing to propose a new system of the operational quantities for external radiations based on protection quantities. The aim of this study is to provide a set of conversion coefficients for use in defining personal dose equivalent for individual monitoring. Fluence-to-effective dose conversion coefficients have been calculated for photons, neutrons, electrons, positrons, protons, muons, pions and helium ions for various incident angles of radiations. The data sets comprise effective dose conversion coefficients for incident angles of radiations from 0 
to 90 in steps of 15 and at 180. Conversion coefficients for rotational, isotropic, superior hemisphere semi-isotropic and inferior hemisphere semi-isotropic irradiations are also included. The conversion coefficients are used to define the operational quantity personal dose equivalent which is being considered by ICRU and utilized for the design and calibration of dosemeters.
Saito, Kimiaki; Yamamoto, Hideaki
Radioisotopes, 63(11), p.519 - 530, 2014/11
This article aims to provide the basic meanings and features of the doses frequently used in the measurements and evaluations of environmental radiation due to the Fukushima Dai-ichi Nuclear Power Plant accident. The following doses are explained and compared: absorbed dose as basic physical quantity; effective dose and equivalent dose for judgment in radiation protection; and ambient dose equivalent 
(10) and individual dose equivalent 
p(10) for radiation measurements.
Saito, Kimiaki; N.Petoussi*; Zankl, M.*
Health Physics, 74(6), p.698 - 706, 1998/06
Times Cited Count：47 Percentile：94.76(Environmental Sciences)no abstracts in English
Tsuchida, Noboru; ; ; ; ; Saito, Minoru;
ANL/RERTR/TM-19, CONF-9209266, 0, p.259 - 266, 1995/00
no abstracts in English
Yamaguchi, Yasuhiro; Yoshizawa, Michio
Proc. of the Int. Radiation Protection Association,Vol. 2, p.1237 - 1240, 1992/00
no abstracts in English
Saito, Kimiaki; N.Petoussi*; Zankl, M.*; R.Veit*; P.Jacob*; G.Drexler*
Journal of Nuclear Science and Technology, 28(7), p.627 - 641, 1991/07
no abstracts in English
Sawa, Kazuhiro; ; Saito, Shinzo
Energy, 16(1-2), p.459 - 470, 1991/00
Times Cited Count：9 Percentile：69.46(Thermodynamics)no abstracts in English
Saito, Kimiaki
Radiation Protection Dosimetry, 35(1), p.31 - 39, 1991/00
Times Cited Count：8 Percentile：66.02(Environmental Sciences)no abstracts in English
Moriuchi, Shigeru; Tsutsumi, Masahiro; Saito, Kimiaki
Hoken Butsuri, 25, p.121 - 128, 1990/00
no abstracts in English
Minami, Kentaro; Murakami, Hiroyuki;
Hoshasen, 13(3), p.18 - 28, 1987/00
no abstracts in English
