JOPSS - Search Results

Journal Articles

Operational quantities for external radiation exposure proposed in ICRU Report 95

Endo, Akira

ESI-News, 43(2), p.37 - 41, 2025/04

The International Commission on Radiation Units and Measurements (ICRU) published ICRU Report 95 in 2020, revising the operational quantities for external exposure. This article provides an overview of the developments in the discussions within the ICRU, the International Commission on Radiological Protection (ICRP), and experts from Japan, and explores the background and process that led the ICRU to revise the operational quantities, as well as future responses and challenges. The article aims to enhance the understanding of the experts of the new operational quantities and to contribute to their smooth implementation in the future.

Journal Articles

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.

Journal Articles

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.

Journal Articles

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.

JAEA Reports

Nuclear Decay Data for Dosimetry Calculation; Revised data of ICRP Publication 38

Endo, Akira; Yamaguchi, Yasuhiro; Eckerman, K. F.*

JAERI 1347, 114 Pages, 2005/02

JAERI-1347.pdf:6.57MB

no abstracts in English

JAEA Reports

Dose evaluation with ICRP Publication 60 at postulated accidents of NSRR, 2003

Kashima, Yoichi; Taki, Mitsumasa; Kikuchi, Masamitsu; Sasajima, Hideo; Nakamura, Takehiko

JAERI-Tech 2003-088, 100 Pages, 2003/12

JAERI-Tech-2003-088.pdf:5.55MB

A new experiment plan is in progress to perform pulse-irradiation experiments at the NSRR with irradiated fuel rods in the high temperature and high pressure capsules. This report describes the results of the public dose evaluation for the design basis accident and postulated accidents with the models that follow the ICRP Publication 60. It was confirmed that the results met the criteria for safety design and siting with ample margins.

Journal Articles

Nuclear decay data used in radiation protection

Endo, Akira

Hoken Butsuri, 38(4), p.308 - 317, 2003/12

https://doi.org/10.5453/jhps.38.308

no abstracts in English

Journal Articles

Reassessment of nuclear decay database used for dose calculation

Endo, Akira; Yamaguchi, Yasuhiro

Journal of Nuclear Science and Technology, 39(Suppl.2), p.1433 - 1436, 2002/08

http://wwwndc.jaea.go.jp/nd2001/proc/pdf/2_1433.pdf

no abstracts in English

JAEA Reports

Compilation of nuclear decay data used for dose calculation; Revised data for radionuclides listed in ICRP publication 38

Endo, Akira; Yamaguchi, Yasuhiro

JAERI-Data/Code 2001-004, 157 Pages, 2001/03

JAERI-Data-Code-2001-004.pdf:11.27MB

New nuclear decay data used for dose calculation have been compiled for 817 radionuclides that are listed in ICRP Publication 38 (Publ.38) and for 6 additional isomers. The decay data were prepared using decay data sets from the Evaluated Nuclear Structure Data File (ENSDF), the latest version in August 1997. Basic nuclear properties in the decay data sets that are important for calculating energies and intensities of emissions were updated by referring to NUBASE. In addition, possible revisions of partial and incomplete decay data sets were done for their format and syntax errors, level schemes, normalization records, and so on. After that, the decay data sets were processed by EDISTR in order to compute the energies and intensities of particles, particles, rays, internal conversion electrons, X rays, and Auger electrons. The compiled data were prepared in two different types of format: Publ.38 and NUCDECAY formats. The decay data will be widely used for dose calculations in radiation protection and will be beneficial to a future revision of ICRP Publ.38.