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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：88.99(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.
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.
Takahashi, Fumiaki
no journal, ,
This lecture focus on the evaluation of equivalent doses in radiation applications other than the medical field. Equivalent dose limits are established based on the recommendations of the International Commission on Radiological Protection (ICRP) in radiation safety standards of Japan. The equivalent doses of workers are evaluated with the operational quantities defined by the International Commission on Radiation Units and Measurements (ICRU). Domestic safety standards are based on the concept of the ICRP's 1990 recommendations, but data used for dose evaluations in accordance with the 2007 recommendations, which replaced these recommendations, have also been made public. In addition, many issues have been pointed out regarding the use of dose in radiation protection, and ICRP published Publ. 147, which clarifies these issues. Efforts are currently underway internationally to resolve the issues presented here. However, consideration and improvement measures are required about issues clarified in Publ.147 within the current protection system.
