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Sato, Rina; Yoshimura, Kazuya; Sanada, Yukihisa; Mikami, Satoshi; Yamada, Tsutomu*; Nakasone, Takamasa*; Kanaizuka, Seiichi*; Sato, Tetsuro*; Mori, Tsubasa*; Takagi, Marie*
Environment International, 194, p.109148_1 - 109148_8, 2024/12
Times Cited Count：6 Percentile：53.54(Environmental Sciences)Assessment of individual external doses from ambient dose equivalents is used for predictive and retrospective assessments where personal dosimeters are not applicable. However, it tends to contain more errors than assessment by personal dosimetry due to various parameters. Therefore, in order to accurately assess the individual dose from ambient dose equivalents, a model that estimates effective doses considering life patterns and the shielding effects by buildings and vehicles, were developed in this study. The model parameters were examined using robust datasets of environmental radiation measured in the areas affected by the Fukushima Daiichi Nuclear Power Station accident in 2020 to 2021. The accuracy of the model was validated by comparison with 106 daily personal doses measured in Fukushima Prefecture in 2020. The measured personal dose was well reproduced by the model-estimated effective dose, showing that the model can be used to assess the individual exposure dose, similar to personal dosimetry. Furthermore, this model is an effective tool for radiation protection, as it can estimate the individual dose predictively and retrospectively by using environmental radiation data.
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.
funabiki, Yuta*; Iyota, Muneyoshi*; Shobu, Takahisa; Matsuda, Tomoki*; Hayashi, Yujiro*; Sano, Tomokazu*; 8 of others*
Journal of Manufacturing Processes, 115, p.40 - 55, 2024/04
Times Cited Count：12 Percentile：82.25(Engineering, Manufacturing)Hosoda, Masahiro*; Nugraha, E. D.*; Akata, Naofumi*; Yamada, Ryohei; Tamakuma, Yuki*; Sasaki, Michiya*; Kelleher, K.*; Yoshinaga, Shinji*; Suzuki, Takahito*; Rattanapongs, C. P.*; et al.
Science of the Total Environment, 750, p.142346_1 - 142346_11, 2021/01
Times Cited Count：44 Percentile：85.83(Environmental Sciences)The biological effects of low dose-rate radiation exposures on humans remains unknown. In fact, the Japanese nation still struggles with this issue after the Fukushima Dai-ichi Nuclear Power Plant accident. Recently, we have found a unique area in Indonesia where naturally high radiation levels are present, resulting in chronic low dose-rate radiation exposures. We aimed to estimate the comprehensive dose due to internal and external exposures at the particularly high natural radiation area, and to discuss the enhancement mechanism of radon. A car-borne survey was conducted to estimate the external doses from terrestrial radiation. Indoor radon measurements were made in 47 dwellings over three to five months, covering the two typical seasons, to estimate the internal doses. Atmospheric radon gases were simultaneously collected at several heights to evaluate the vertical distribution. The absorbed dose rates in air in the study area vary widely between 50 nGy h
and 1109 nGy h. Indoor radon concentrations ranged from 124 Bq m
to 1015 Bq m. That is, the indoor radon concentrations measured exceed the reference levels of 100 Bq m recommended by the World Health Organization. Furthermore, the outdoor radon concentrations measured were comparable to the high indoor radon concentrations. The annual effective dose due to external and internal exposures in the study area was estimated to be 27 mSv using the median values. It was found that many residents are receiving radiation exposure from natural radionuclides over the dose limit for occupational exposure to radiation workers. This enhanced outdoor radon concentration might be as a result of the stable atmospheric conditions generated at an exceptionally low altitude. Our findings suggest that this area provides a unique opportunity to conduct an epidemiological study related to health effects due to chronic low dose-rate radiation exposure.
Yoshizawa, Michio; Endo, Akira
JAERI-Conf 2003-002, 166 Pages, 2003/03
JAERI-Conf-2003-002.pdf:9.79MB
The present report is Proceedings of the Third Workshop on Dosimetry for External Radiations, held at the Tokai Research Establishment, Japan Atomic Energy Research Institute (JAERI), in November 28-29, 2002. The proceedings comprises 16 papers and a summary of general discussion. The Third Workshop, subtitled "On an opportunity of the completion of the facility of calibration standards for neutron at JAERI", focused on neutron dosimetry and included presentations on the status of international neutron standards, the development of calibration techniques of neutron dosimeters using accelerator neutron sources, and dosimetry for high-energy neutrons. The workshop identified the directions for the future research and development in this field.
Endo, Akira; Yamaguchi, Yasuhiro; Sakamoto, Yukio; Yoshizawa, Michio; Tsuda, Shuichi
Radiation Protection Dosimetry, 93(3), p.207 - 214, 2001/00
Times Cited Count：6 Percentile：42.88(Environmental Sciences)no abstracts in English
Department of Health Physics; Safety Division, Naka; Safety Division, Takasaki; Radiation Control Division, Oarai; Utilities and Safety Division, Kansai; Operation Safety Administration Division, Mutsu
JAERI-Review 2000-001, p.225 - 0, 2000/03
JAERI-Review-2000-001.pdf:9.42MB
no abstracts in English
Department of Health Physics; Safety Division, Naka; Safety Division, Takasaki; ; ; Operation Safety Administration Division, Mutsu
JAERI-Review 98-015, 239 Pages, 1998/12
no abstracts in English
Department of Health Physics; Safety Division, Naka; Safety Division, Takasaki; ; ; Operation Safety Administration Division, Mutsu
JAERI-Review 97-016, 248 Pages, 1997/12
JAERI-Review-97-016.pdf:7.82MB
no abstracts in English
Department of Health Physics; Safety Division, Naka; Safety Division, Takasaki; ;
JAERI-Review 96-014, 236 Pages, 1996/10
JAERI-Review-96-014.pdf:7.25MB
no abstracts in English
Department of Health Physics; Safety Division, Naka; Safety Division, Takasaki; ; Operation Safety Administration Division, Mutsu;
JAERI-Review 95-020, 264 Pages, 1995/11
JAERI-Review-95-020.pdf:8.68MB
no abstracts in English
Department of Health Physics; Safety Division, Naka; Safety Division, Takasaki; ; Operation Safety Administration Division, Mutsu;
JAERI-Review 94-007, 262 Pages, 1994/11
JAERI-Review-94-007.pdf:7.85MB
no abstracts in English
Department of Health Physics; Safety Division, Naka; Safety Division, Takasaki; ; Operation Safety Administration Division, Mutsu;
JAERI-M 93-172, 291 Pages, 1993/09
no abstracts in English
Department of Health Physics; ; Safety Division, Naka; Safety Division, Takasaki; ; ; Operation Safety Administration Division, Mutsu; ;
JAERI-M 92-144, 301 Pages, 1992/10
no abstracts in English
Sato, Nobuyuki; ; Kobayashi, Makoto; Nakazawa, Takashi; ; ; Ikezawa, Yoshio
Proc. of the Int. Conf. on Radiation Effects and Protection, p.440 - 445, 1992/00
no abstracts in English
Department of Health Physics; ; ; ; ; ;
JAERI-M 91-171, 294 Pages, 1991/11
no abstracts in English
; Yanagihara, Satoshi; Sukegawa, Takenori; Tanaka, Mitsugu
Nihon Genshiryoku Gakkai-Shi, 33(6), p.574 - 584, 1991/06
Times Cited Count：0 Percentile：0.00(Nuclear Science & Technology)no abstracts in English
Department of Health Physics; ; ; ; ; ;
JAERI-M 90-224, 270 Pages, 1990/12
no abstracts in English
Department of Health Physics; ; ; ; ; ;
JAERI-M 89-212, 334 Pages, 1989/12
no abstracts in English
Hertel, N. E.*; Bartlett, D. T.*; Dietze, G.*; Bordy, J.-M.*; Endo, Akira; Gualdrini, G.*; Pelliccioni, M.*; Ambrosi, P.*; Siebert, B. R. L.*; Veinot, K.*; et al.
no journal, ,
The International Commission on Radiation Units and Measurements (ICRU) defines a set of operational quantities for use in radiation measurements that provides assessment of the protection quantities recommended by International Commission for Radiological Protection (ICRP). The ICRU operational quantities in current use was defined about 30 years ago. ICRU Report Committee 26 has examined the rationale for operational quantities taking into account the changes in the definitions of the protection quantities and the changes in the fields of application of the operational quantities and protection quantities. The considerations have included the range of types and energies of particles contributing to doses to workers and members of the public. The relationship of the existing recommended operational quantities to the protection quantities has been investigated, as has the impact of changes in routine measurement practice, including instrument design and calibration. The committee has proposed a set of operational quantities which differs from the previous quantities. The major change in the proposed set of quantities is the redefinition of the operational quantities for area monitoring from doses computed at a depth in the ICRU sphere to ones based on particle fluence and the relationship to the protection quantities, effective dose, and equivalent dose to the lens of the eye, and local skin.
