Annual report for 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.

ICRP Publication 116 "Conversion Coefficients for Radiological Protection Quantities for External Radiation Exposures"; Summary

Endo, Akira

Isotope News, (736), p.34 - 37, 2015/08

http://www.jrias.or.jp/books/pdf/201508_TRACER_ENDO.pdf

Japanese translation of ICRP Publication 116 entitled "Conversion Coefficients for Radiological Protection Quantities for External Radiation Exposures" was published by the Japan Radioisotope Association in March 2015. The book gives fluence to dose conversion coefficients for both effective dose and organ absorbed doses for various types of external exposures, consistent with the 2007 Recommendations of the ICRP. A complete set of conversion coefficients is provided in an accompanying CD in ASCII format and Microsoft Excel software. This article overviews ICRP Publication 116 and its impact to practice of radiation protection.

Annual report on the present state and activities of the Radiation Protection Department, Nuclear Fuel Cycle Engineering Laboratories in fiscal 2009

Radiation Protection Department

JAEA-Review 2015-003, 187 Pages, 2015/03

JAEA-Review-2015-003.pdf:18.34MB

This annual report summarizes the various activities on radiation control at the nuclear fuel cycle facilities in Nuclear Fuel Cycle Engineering Laboratories, which were undertaken by the Radiation Protection Department in fiscal 2009. In the Laboratories, the Tokai Reprocessing Plant (TRP), MOX fuel fabrication facilities, the Chemical Processing Facility (CPF), and various other radioisotopes and uranium research laboratories have been operated. The Radiation Protection Department is responsible for the radiation control in and around the facilities, including personnel monitoring, workplace monitoring, consultation on radiological work planning and evaluation, monitoring of gaseous and liquid waste effluents, environmental monitoring, radiological standards, maintenance of radiation monitoring instruments, quality management, and the related research. In fiscal 2009, the results of radiological monitoring showed the situation to be normal, and no radiological incident or accident occurred. The maximum annual effective dose to radiation workers was 9.7 mSv and the mean annual effective dose was 0.2 mSv. Individual doses were kept within the annual dose limit specified in the safety regulations. The estimated effective dose caused by gaseous and liquid effluents from the TRP to imaginary members of the public around the Laboratories was 1.810 mSv. The environmental monitoring and effluent control were performed appropriately in compliance with safety regulation and standards. As for the quality management activities, the inspection by the government, the internal audit, and the maintenance to revise the documents have been continued in accordance with the quality management system which had been introduced to safety regulation since fiscal 2004.

Discussion on dose concept used for radiation protection

Yamaguchi, Yasuhiro

FBNews, (345), p.1 - 3, 2005/09

http://www.c-technol.co.jp/pdf/345fbn.pdf

no abstracts in English

11th International Congress of the International Radiation Protection Association

Kinase, Sakae; Saegusa, Jun; Sagawa, Hiroyuki*; Hosoda, Masahiro*

Hoken Butsuri, 39(4), p.307 - 311, 2004/12

http://ci.nii.ac.jp/naid/110003375561

no abstracts in English

Personnel protection system in J-PARC linac

Hiroki, Fumio; Yoshikawa, Hiroshi; Takeuchi, Yasunori*; Kudo, Kikuo*

Proceedings of 1st Annual Meeting of Particle Accelerator Society of Japan and 29th Linear Accelerator Meeting in Japan, p.159 - 161, 2004/08

The main purpose of Personnel Protection System (PPS) is to protect people from radiation exposure. From the viewpoint of it, important features of the Japan Proton Accelerator Research Complex (J-PARC) are (1) the beam power as high as 1MW, and (2) a lot of beam-line entrances apart from the main control room. The first feature requires the beam interlock function of PPS to be more reliable than ever. The second one is dealt with the access control function of PPS, with which the remote access control from the central control room is enabled. In this paper, we report the beam interlock and access control functions of the PPS.