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Tsujimura, Norio
Hokeikyo Nyusu, (71), p.2 - 5, 2023/04
The TLD badge, a personal dosimeter using a thermoluminescence dosemeter, currently in operation at the Nuclear Fuel Cycle Engineering Laboratories of the Japan Atomic Energy Agency (JAEA-NCL), was developed in collaboration with Matsushita Industrial Co., Ltd. (now Panasonic System Solutions Japan Co., Ltd.), and was put into operation in 1982. Since then, the TLD badge has been used not only at NCL but also in Japan and overseas for a long time. However, the TLD badge system will no longer be accepted for new production by the manufacturer in 2019, and maintenance and repair services for the TLD readers will cease in 2027. In addition, a performance accreditation system for personal dosimetry will be introduced in Japan, and accredited personal dosemeters will be required under the revised enforcement regulations of the RI Law (from October 2023). Given these changes in the circumstance, NCL has decided to abandon the in-house measurement service and switch to commercially available accredited personal dosemeters in the future. In this paper, the development history and design concept of the TLD badge are outlined along with the historical development of the operational quantities, and the findings obtained from more than 40 years of operational experience with the TLD badge are presented.
Takahashi, Fumiaki
Genshiryoku No Ima To Ashita, p.109 - 111, 2019/03
The Atomic Energy Society of Japan has planned to publish a document for public, entitled "Current and tomorrow of atomic energy, -Experiences from the accident at the Tokyo Electronic Power Company Fukushima Dai-ichi NPPs-". The documents give us basics and usages of radiations, in addition to nuclear power plants and the accident at TEPCO Fukushima Dai-ichi NPPs. This manuscript explains physical quantities (e.g., absorbed dose), protection quantities and operational quantities that are used for radiation measurement and protection. The unit of radioactivity is also explained, because radioactivity is measured for work places in a radiation facility for internal exposure protection. In addition, radiation dose constants that relate radiation dose to the activity are also introduced, as useful radiation units for radiation protection.
Otto, T.*; Hertel, N. E.*; Bartlett, D. T.*; Behrens, R.*; Bordy, J.-M.*; Dietze, G.*; Endo, Akira; Gualdrini, G.*; Pelliccioni, M.*
Radiation Protection Dosimetry, 180(1-4), p.10 - 16, 2018/08
Times Cited Count：19 Percentile：89.32(Environmental Sciences)Report Committee 26 of the ICRU proposes a set of operational quantities for radiation protection for external radiation, directly based on effective dose and for an extended range of particles and energies. It is accompanied by new quantities for estimating deterministic effects to the eye lens and the local skin. The operational quantities are designed to overcome the conceptual and technical shortcomings of those presently in use. This paper describes the proposed operational quantities, and highlights the improvements with respect to the present legal monitoring quantities.
Endo, Akira
Hoken Butsuri, 52(1), p.39 - 41, 2017/03
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.
Manabe, Kentaro
Hoken Butsuri, 52(1), p.35 - 38, 2017/03
Health Physics Seminar 2016 was held at the Osaka Science & Technology Center with 150 participants on Nov. 2, 2016. The seminar was consisted of three themes: "current movements of protection and operational quantities", "future risk communications inspired by the Fukushima accident", and "effects of low dose radiation on human". Eminent specialists gave lectures about the news in their particular fields and suggestions to problems. In addition, a special lecture entitled "recent movements of issues about Act on Prevention of Radiation Hazards due to Radioisotopes, etc." was given by a specialist of the Secretariat of Nuclear Regulation Authority. This lecture introduced the examples of trouble incidents, reports on implementation status of inspections, results of Integrated Regulatory Review Service by IAEA, etc. There were vigorous questioning and discussions through the seminar. This document reported the summary of the lectures and discussions, and the author's impressions of the seminar.
Yamaguchi, Yasuhiro
FBNews, (345), p.1 - 3, 2005/09
no abstracts in English
Saegusa, Jun; Yoshizawa, Michio; Tanimura, Yoshihiko; Yoshida, Makoto
Radioisotopes, 51(1), p.26 - 33, 2002/01
no abstracts in English
Yoshizawa, Michio; Tsujimura, Norio*
Hoken Butsuri, 36(1), p.18 - 23, 2001/03
no abstracts in English
Yoshizawa, Michio
Hokeikyo Nyusu, (23), p.2 - 4, 1999/03
no abstracts in English
Yoshizawa, Michio; Mizushita, Seiichi
Hoken Butsuri, 34(3), p.319 - 322, 1999/00
no abstracts in English
Yoshizawa, Michio
Hoken Butsuri, 33(1), p.7 - 11, 1998/00
no abstracts in English
Yamaguchi, Yasuhiro
Hoken Butsuri, 33(1), p.12 - 15, 1998/00
no abstracts in English
Yamaguchi, Yasuhiro; Endo, Akira
JAERI-Conf 96-011, 63 Pages, 1996/07
no abstracts in English
Endo, Akira
no journal, ,
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.
(10) to relate dosemeter readings to effective doseTsujimura, Norio
no journal, ,
no abstracts in English
Endo, Akira
no journal, ,
Radiation protection of medical staff is a fundamental and key issue in diverse uses of radiations for diagnostic and therapeutic purposes. It requires the quantification of the extent of exposure of the human body to ionizing radiations of wide energy range, such as X-rays, various types of radiations emitted from radiopharmaceuticals, neutrons from medical-use accelerators, and so on. 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. This presentation overviews the dosimetry system for radiation protection and introduces recent discussion on the operational quantities.
Takahashi, Fumiaki
no journal, ,
ICRU (International Commission on Radiation Unit Measurement) and ICRP (International Commission on Radiological Protection) define various radiation doses to achieve the purpose of radiation protection. The definitions of these radiation doses have been changed to reflect the latest knowledge and to correspond to expansions of radiation utilization. In 2020, ICRU and ICRP have just announced the change of the operational quantities that are utilized in radiation monitoring for external exposures. From these backgrounds, a research conference will be held to recognize the system of "quantity" concerning radiations and to share the latest trends and issues to be addressed in the field of radiological protection. In this presentation, definitions of the radiation doses given by ICRU and ICRP are reviewed and explained how they are applied in the implementation of radiation protection. In addition, issues and points to keep in mind are introduced for incorporating the ICRP 2007 Recommendation into radiation standards in Japan.
Takahashi, Fumiaki; Sato, Kaoru; Satoh, Daiki
no journal, ,
In 2010, the International Commission on Radiological Protection (ICRP) indicated that the current operational quantities would underestimate effective doses based upon ICRP 2007 Recommendations. The International Commission on Radiation Unit and Measurement (ICRU) published new operational quantities in 2020. It can be required to use radiations instruments and dosimeters that correspond to the current operation quantities, even after Japanese standards for radiation safety are revised by taking account for ICRP 2007 Recommendations. Thus, we have analyzed relationships between current operational quantities and effective doses (current and new) for external neutron exposure by using spectra compiled in IAEA report. It is cleared that the current operational quantities can safely estimate the new effective dose. In addition, ratio of the new effective dose to the current operational quantity strongly depends on energy spectra in neutron fields.
Yoshitomi, Hiroshi; Tsuji, Tomoya; Nishino, Sho; Fukami, Tomoyo; Tanimura, Yoshihiko
no journal, ,
no abstracts in English
Yoshitomi, Hiroshi; Tsuji, Tomoya; Fukami, Tomoyo; Nishino, Sho; Tanimura, Yoshihiko
no journal, ,
no abstracts in English
