A Key element of internal dosimetry for members of the public

Endo, Akira

Annals of the ICRP, 52(4), p.5 - 7, 2024/12

https://doi.org/10.1177/01466453241241770

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.

Annual report of Nuclear Emergency Assistance and Training Center (April 1, 2022 - March 31, 2023)

Nuclear Emergency Assistance and Training Center

JAEA-Review 2023-026, 54 Pages, 2023/12

JAEA-Review-2023-026.pdf:3.26MB

The Japan Atomic Energy Agency (JAEA) is one of the designated public corporations, which is the agency dealing with emergency situations in cooperation with the Japanese and local governments under the Disaster Countermeasures Basic Act and under the Armed Attack Situation Response Law. JAEA has, therefore, responsibilities of providing technical assistances to the Japanese and local governments in case of nuclear or radiological emergencies based on these acts. To fulfill the assistances, the JAEA has prepared the Nuclear Emergency Support Measures Regulation, Disaster Prevention Work Plan and Civil Protection Work Plan. The Nuclear Emergency Assistance and Training Center (NEAT) is the main center of the technical assistance in case of emergency, and dispatches experts of JAEA, supplies equipment and materials and gives technical advice and information, to the Japanese and local governments for emergency based on the regulation and plans. In normal time, the NEAT provides the technical assistances such as the exercises and training courses concerning the nuclear preparedness and response to the JAEA experts and to emergency responders including the Japanese and local government officers. This report introduces the results of activities in Japanese Fiscal Year 2022, conducted by the NEAT.

Annual report of Nuclear Emergency Assistance and Training Center (April 1, 2021 - March 31, 2022)

Nuclear Emergency Assistance and Training Center

JAEA-Review 2022-044, 58 Pages, 2022/12

JAEA-Review-2022-044.pdf:3.83MB

The Japan Atomic Energy Agency (JAEA) is one of the designated public corporations, which is the agency dealing with emergency situations in cooperation with the Japanese and local governments under the Disaster Countermeasures Basic Act and under the Armed Attack Situation Response Law. JAEA has, therefore, responsibilities of providing technical assistances to the Japanese and local governments in case of nuclear or radiological emergencies based on these acts. To fulfill the assistances, the JAEA has prepared the Nuclear Emergency Support Measures Regulation, Disaster Prevention Work Plan and Civil Protection Work Plan. The Nuclear Emergency Assistance and Training Center (NEAT) is the main center of the technical assistance in case of emergency, and dispatches experts of JAEA, supplies equipment and materials and gives technical advice and information, to the Japanese and local governments for emergency based on the regulation and plans. In normal time, the NEAT provides the technical assistances such as the exercises and training courses concerning the nuclear preparedness and response to the JAEA experts and to emergency responders including the Japanese and local government officers. This report introduces the results of activities in Japanese fiscal year 2021, conducted by the NEAT.

Variation of internal doses caused by differences in physical characteristics between the average Japanese and the ICRP's reference man which is based on the standard data of Caucasians in the dosimetric methodology in conformity to the 2007 Recommendations

Manabe, Kentaro; Sato, Kaoru; Takahashi, Fumiaki

Journal of Nuclear Science and Technology, 59(5), p.656 - 664, 2022/05

https://doi.org/10.1080/00223131.2021.1997663

It is known that internal doses depend on the physical characteristics of an evaluation subject. Internal dose coefficients provided by the International Commission on Radiological Protection (ICRP) are evaluated using the characteristics of the standard Caucasian. It is important to grasp the variations of doses due to the differences in characteristics between Japanese and Caucasian when the dose coefficients of ICRP are applied to Japanese. This study evaluated dose coefficients using specific absorbed fraction (SAF) data based on the average adult Japanese physique which was developed by modification of the existing Japanese SAF data with additional calculations to make the existing data fit to the current dosimetric methodology of ICRP and compared them to those provided by ICRP. As a result, the discrepancies in dose coefficients were smaller than plus or minus 10% in most intake conditions. However, some intake conditions indicated varieties over 40% due to the differences in organ masses, amount of adipose tissues around the thoracic cavity, and so on. This information is useful in application of ICRP's dose coefficients to population of which physical characteristics are different from those of Caucasian. Further, the Japanese SAF data is published as an appendix of this paper.

Annual report of Nuclear Emergency Assistance and Training Center (FY 2020 and Previous 20 Years)

Nuclear Emergency Assistance and Training Center

JAEA-Review 2021-039, 98 Pages, 2021/12

JAEA-Review-2021-039.pdf:5.99MB

Japan Atomic Energy Agency (JAEA) is one of the designated public corporations, dealing with emergency situations in cooperation with the Japanese government under the Disaster Countermeasures Basic Act and under the Armed Attack Situation Response Law. JAEA provides technical assistances to the government in case of nuclear or radiological emergencies. JAEA has prepared the Nuclear Emergency Support Measures Regulation, Disaster Prevention Work Plan and Civil Protection Work Plan. Nuclear Emergency Assistance and Training Center (NEAT) is the main center of the technical assistance in case of emergency, and dispatches experts, supplies equipment and materials and gives technical advice to the government. Moreover, NEAT provides the technical exercises and training courses concerning the nuclear emergency preparedness and response to emergency responders. This report introduces the results of activities in FY 2020, during the third medium and long-term plan from FY 2015 to 2021 as Chapter 1. Chapter 2 summarizes activities in 20 years since FY 1999.

Annual report of Nuclear Emergency Assistance and Training Center (April 1, 2019 - March 31, 2020)

Nuclear Emergency Assistance and Training Center

JAEA-Review 2020-016, 67 Pages, 2020/09

JAEA-Review-2020-016.pdf:4.09MB

The Japan Atomic Energy Agency (JAEA) is one of the designated public institutions, which is an agency dealing with an emergency situation in cooperation with the Japanese and local governments under the Disaster Countermeasures Basic Act and under the Armed Attack Situation Response Law. JAEA has, therefore, responsibilities of providing technical assistances to the Japanese and local governments in case of nuclear or radiological emergencies based on these Acts. To fulfill the assistances, the JAEA has prepared the Nuclear Emergency Support Measures Regulation, Disaster Prevention Work Plan and Civil Protection Work Plan. The Nuclear Emergency Assistance and Training Center (NEAT) is the main center of the technical assistance in case of emergency, and dispatches experts of JAEA, supplies equipment and materials and gives technical advice and information, to the Japanese and local governments for emergency based on the regulation and plans. In normal time, the NEAT provides the technical assistances such as the exercises and training courses concerning the nuclear preparedness and response to the JAEA experts and also to emergency responders including the Japanese and local government officers. This report introduces the results of activities in Japanese Fiscal Year 2019, conducted by NEAT in accordance with the third medium and long-term plan for the period from Japanese Fiscal Year 2015 to 2021.

Assessment of inhomogeneity of exposure to radiation workers in homogeneous exposure situations in Nuclear Industry and Accelerator Facility by using Monte Carlo calculations coupled with a mathematical phantom; Exposure to the lens of the eye in homogeneous exposure situation due to gamma and beta rays

Kowatari, Munehiko; Yoshitomi, Hiroshi

Radioisotopes, 68(9), p.595 - 603, 2019/09

https://doi.org/10.3769/radioisotopes.68.595

Estimating internal dose coefficients of short-lived radionuclides in accordance with ICRP 2007 Recommendations

Manabe, Kentaro; Sato, Kaoru; Takahashi, Fumiaki

Journal of Nuclear Science and Technology, 56(5), p.385 - 393, 2019/05

https://doi.org/10.1080/00223131.2019.1585988

At high energy accelerator facilities, various radionuclides are produced by nuclear reactions of high energy particles with structure and/or ambient air of the facilities. Consequently, the radionuclides are potential sources of internal exposure for works of the facilities. However, the International Commission on Radiological Protection (ICRP) do not provide dose coefficients, which are committed effective doses per intake, for the short-lived radionuclides whose half-lives are shorter than 10 minutes in accordance with the ICRP 2007 Recommendations. Then, we estimated the dose coefficients for inhalation and ingestion of these short-lived radionuclides in accordance with the ICRP 2007 Recommendations. In addition, we compared the dose coefficients with those in accordance with the ICRP 1990 Recommendations. As a result, a decreasing tendency was shown in the dose coefficients for inhalation cases; an increasing tendency was observed in those for ingestion cases. It was found that these changes in dose coefficients were mainly caused by the revision of the dose calculation procedures, alimentary tract models. The result of this study will be useful for planning of radiation protection at the high energy facilities.

Recent discussion on protection quantities and operational quantities by ICRP and ICRU

Endo, Akira

Hoken Butsuri, 52(1), p.39 - 41, 2017/03

https://doi.org/10.5453/jhps.52.39

Radiological protection requires the quantification of the extent of exposure of the human body to ionizing radiation. To this end, the International Commission on Radiological Protection (ICRP) and the International Commission on Radiation Units and Measurements (ICRU) developed a dosimetry system consisting of protection quantities and operational quantities. The existing dosimetry system has been successfully used in radiological protection practice and regulations. Nevertheless, the system has some limitations and needs further improvements to consider changes in the fields of radiological protection. ICRP and ICRU have been discussing the issues to propose an alternative system of radiation dosimetry. This presentation overviews recent discussion on the protection quantities and operational quantities by ICRP and ICRU and the proposed dosimetry system for radiological protection.

Experience gained from the Fukushima-Daiichi accident as input for developing a technical knowledge base including remediation technologies

Miyahara, Kaname; Iijima, Kazuki; Saito, Kimiaki

Jiban Kogakkai-Shi, 63(11/12), p.62 - 69, 2015/11

AA2015-0380.pdf:1.64MB

http://ci.nii.ac.jp/naid/110010010291

This review provides a concise overview of knowledge and experience gained from the activities for environmental remediation after the Fukushima Dai-ichi accident as input for developing a technical knowledge base including remediation technologies which is translated into actions that enable the rapid return of evacuees. It is reflecting JAEA's key role in the research associated with both remediation of contaminated areas and the natural processes influencing contamination migration in non-remediated areas, working together with a number of Japanese and international organisations and research institutes. This review also provides a perspective on the future actions required to remediate areas outside the Fukushima Dai-ichi site.